ML061730173
| ML061730173 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/20/1992 |
| From: | Marx D Vermont Yankee |
| To: | Kooiker B NRC Region 1, State of VT, Agency of Natural Resources |
| References | |
| %dam200611 | |
| Download: ML061730173 (72) | |
Text
tfZ August 20, 1992 Mr. Brian Kooiker Permits, Compliance, and Protection Departn~ent of Environmental Conservation Agency of Natural Resources State of Vermont 103 South Main Street-The Annex Waterbury, VT 05671-0405
Subject:
NPDES unplanned discharge, August 14, 1992.
Reference:
NPDES Permit No. 3-1199, VT0000264.
Dear Mr. Kooiker:
This letter is written to document an incident which occurred at the Vermont Yankee Nuclear Power Station on August 14, 1992 which resulted in an unplanned release to the Connecticut River at Vernon of a limited amount of water slightly contaminated with radionuclides.
The incident was verbally reported to Ms Nancy Manley of the Agency on August 18th at 8:30 a.m. and earlier to Mr William Sherman, Vermont State Nuclear Engineer, on August 17th at 10:00 a.m.
A description of the event is attached. The incident is still under evaluation by Vermont Yankee personnel and will result in a Corrective Action Report.
Current radiological analyses show that limits established by the Nuclear Regulatory Commission have not been exceeded. The event will be reported in the semiannual Radiological Effluent Report.
In the event you should require further information, please do not hesitate to call.
Sincerely, Daniel J. Marx, Ph.D.
Environmental Scientist Attachment, VYNPC, 8/20/92.
Attachment, VYNPC, 8/20/92 Overflow of Condensate Demineralizer Backwash Receiving Tank On August 14, 1992 at approximately 1330, while backwashing the B condensate demineralizer and transferring the contents to the condensate demineralizer backwash tank, the electric pump which transfers the water from the tank to radwaste failed, resulting in the backwash receiving tank overflowing onto the floor. The water was radioactively contaminated and contained some resin material. The floor in the vicinity of the tank was flooded to a depth of approximately 1-2 inches.'%
Samples" taken in a nearby sump indicated the presence of radioactive Iodine and Tritium.
The sump pumps are designed to cycle if required by level so it is possible that some contaminated water was discharged to the river by way of the service water system (10,000 gpm) and then into the main circulating water system (360,000 gpm) before entering the Connecticut River.
The precise volume of contaminated water that may have been discharged to the river is estimated to be less than 15 gallons. Radiation monitors and samples at the point of discharge did not record any evidence of radioactivity and remained normal during the entire event.
Vermont Yankee personnel isolated the sump pumps and terminated the potential discharge at approximately 1430.
Based on radiological analysis of samples taken from the floor, sumps, and the discharge structure, and assuming bounding conditions, Vermont Yankee calculated that Technical Specifications and NRC 10CFR requirements and limits were not exceeded and the event was not reportable to the NRC. The calculated parameter values were also below Vermont Department of Health Radiological Health limits and the NPDES Permit limits.
The calculated values were based on the extremely conservative assumption that radioactive water was pumped out of the sumps and discharged through the normal flow path to the river continuously during the event. The calculation assumes dilution by the flow of the circulating water system (360,000 gpm) occurring concurrently with the discharge.
The actual volume of radioactive water discharged is estimated to be three orders of magnitude below the bounding calculated values, or less than 15 gallons. Connecticut River flow at the time of the incident was approximately 6000 cfs.
DJM.8/20/92
SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases - The "Calculated Value is based upon ithe assumption that 1000 gallons of radioactive water was pumped out of the TB Clean Sump and discharged, through the normal flow path, .to the riVer.
The calculation assumes dilution by the flow of Circulating Water(360000 gpm) Occurring concurrently with this discharge..
APPLICABLE LIMITS LIQUID 'RELEASE CalculatedValue TECHNICAL SPECIFICATIONS
-Liquid Effluents: Concentrations 1)T.S.3.8.A.1 - I1 MPC as determined by 10CFR20, App.B, Table II, Col. 2 conc.(Noble Gases excluded) 2.92E--3 MPC's 2)T.S.3.8.A.I - Total'Noble Gases:.
Conc. < 2E-4 uci/cc i.:16E-9 uci/cc Liquid Effluents: Dose. * . - "."* '
I)Total Body Dose.-T.S.3.8.B.* -.
1.5.mrem in any-quarter, 3 mrem total for year... 127E-1 mrem 2)Organ Dose -. T.S.3.8.B.1:-..
'5 mrem in any quarter, 10 mrem total for year 6.23E-5 mrem 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when aVeraged.over one hour 2. 43E-4 MPC's.
NPDES REPORTING REQUIREMENTS.
Unplanned Releases Yes 10CFR20 App B, Table II, Col.2 (1 MPC) '2.92E-3 MPC's
- Total Radionuclides(excluding tritium) shall be K 5 curies per year 3.57E-5 curies Total Tritium shall be K 5 curies per year 4.02E-.5 curies' Dose Calendar quarter -
- 1.5 mrem total body 1.27E-7 mrem
- 5mrem to any organ 6-.23E-5 mrem Calendar year S 3 mrem total body 1.27E-7 mrem*
S 10 mrem to any organ 6.23E-5 mrem m
- pn -6.5' ts.5 itanaara.Units .7.6 Flow'- 14.4 million gallons per day'.. 1000gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive Material(except tritium and dissolved noble gases S IE-7 uci/mlW 4.10E-9 uci/ml Additional action level4
>2% of iE-7(or 2E-9)uci/ml* 4.10E-9 uci/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days.
- 1 (see regulation for additional details)
>4% of IE-7(or 4E-9)uci/mlW. 4.10E-9 uci/ml Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, f0llowup report to Vt. Board of Health(see regulation for additional details)
- 3. Dissolved noble gases - K 4E-5 uci/ml
.(see regulation for additional quarterly 1.16E-9 uci/ml limits) I Performed by ,2 Reviewed b!9?-
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SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases - The "Calculated Value is based upon the assumption that 1000 gallons of radioactive water was pumped Out of the TB Clean Sump and discharged, through the normal flow.path, to the river..:
The calculation' assumes dilution by. the flow of - Circulating Water(360000 gpm) occurring concurrently with this discharge .
APPLICABLE LIMITS RELEASE-.
- - .LIQUID
.* ... .'Calcula~te~dValue .
.TECHNICAL SPECIFICATIONS
- Liquid Effluents: Concentrations I S )T
. 3 a*A- I - ýL"+/- I . Ufr Ls e1LL+/-ntuU by 10CFR20, App.B, Table II, Col. 2 conc.(Noble Gases excluded) 2.92E-3 MPC's 2)T.S.3.8.A.1 - Total Noble Gases.
Conc.*S 2E-4 uci/cc 1.16E-9 uci/cc Liquid Effluents: Dose 1)Total Body Dose -T.S.3.8.B.1 -
1.5 mrem in any quarter,,
3 mrem total for year 1.27"E-7 mrem 2)Organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year 6.23E-5 mrem IOCFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.43E-4 MPC's NPDES REPORTING REQUIREMENTS...
Unplanned Releases Yes 10CFR20 App B, Table II, Col.2 (1 MPC) -:2.92E-3 MPC's Total Radionuclides(excluding tritium):
shall be K 5 curies per year 3.57E-5 curies Total Tritium shall be
- 5 curies per.year 4.02E-5 curies Dose Calendar quarter - < 1.5 mrem total body -. 1.27E-7 nrem Calendar- < 5 mrem to any organ 6.23E-5 mrem Calendar year - K 3 mrem total body 1.27E-7 1':. mrem.
< 1-0 mrem to any organ
- 6.23E-5 mrem
- .pH - 6.5 to 8.5 Standard.Units" ..
".7.6 Flow - 14.4 million gallons per day . 1000gallons
VEtAMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive Material(except tritium and dissolved noble gases K 1E-7 uci/mlW 4.10E-9 uci/ml Additional action levelfs-
>2%.of 1E-7(or 2E-9)uci/mli*r. 4.10E-9 uci/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days (see regulation for additional details)
.-W o X.I-1kor 4z-9)uci/m1T 4.10E-9 uci/ml
- Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
- 3. Dissolved noble gases -. S 4E-5 uci/ml 1.16E-9 uci/ml (see regulation for additional quarterly limits)
Performed by Reviewed bYZ
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SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases - The "Calculated Value is based upon !the a'uiption" that 1000 gallons of radioactive water, was. pumped out of the TB Clean.
Sump and discharged, through the normal flow *path, .to the river..:.!
The calculation assumes dilution by the lf ow ..of Circulating Water(360000 gpm) occurring concurrently with this discharge-..
APPLICABLE LIMITS
- ... " . .LIQUID. . " :.'. " t. : " :*. .,;:.CalculatedValue RELEASE * ;-"
TECHNICAL SPECIFICATIONS
- Liquid Effluents: Concentrations
" 1)T.S.3.8.A.1 - < 1 MPC as determined by 10CFR20, App.B, Table.II, Col. .2
- conc.(Noble Gases excluded) .2.92E-3 MPC's 2)T.S.3.8.A.1 - Total Noble Gases .. '.....
.. Conc. < 2E-4 uci/cc . .. 1..16E-9 uci/cc.
Liquid Effluents: Dose
- " 1)Total Body Dose -T.S.3.8.B.1 -
.1.5 mrem in any quarter, 3 mrem total for year 1.27E-7 mrem 2)Organ Dose- T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year 6.23E-5 mrem 10CFR50.72 REPORTING REQUIREMENTS "'"..
2 times MPC when averaged over one hour 2.43E-4 MPC'S NPDES REPORTING REQUIREMENTS Unplanned Releases Yes
.IW' 10CFR20 1 )ADf 9 App B, Table II, Col.2 Total Radionuclides(excluding tritium)-*
shall be S 5 curies per year 3.57E-5 curies
- . Total Tritium shall be < 5.curies per year. 4.02E-5 curies Dose'. .
. Calendar quarter - .1.5 mrem total body .i.27E-7 m'orem
-". 5 mrem to any organ 6.23E-5 mrem.
Calendar year - <
K 3 mrem total body .. : . 1.27E-7 mreim.u
- < 10 mremto any organ...'. 6.23E-5 mrem pH - :6.5 to 8.5 Standard*Units "."" " .7.6 ..
- lo- 144-ilio.glln per da *l....O. .".a.-.. ...
l°. s Flow* - .14.4 million gallons per..day 1000gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
.1. Radioactive Material(except tritium and dissolved noble gases 11E-7 uci/ml* *4.1OE-9 uci/mi Additional action levels*
>2% of 1E-7(or 2E-9)uci/ml* *4.1OE-9 uci/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days.
- 1 (see regulation for additional details)
I
>4%* of IE-7(or 4E-9)uci/mlW 4. 1OE-9 uci/ml Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
. (see regulation for additional*quarterly.
limits) " . * *
- 3. Dissolved noble gases - 4E-5 uci/ml 1.16E-9 uci/ml
- (see regulation for additional quarterly .
limits) .....
Performed by ..
Reviewed b S-tre owo4,re
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SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92.
Bases - The "Calculated Value is based upon' the as'umption that 12000 gallons of radioactive water was pumped out, of the TB Clean Sump and discharged, through the normal flow path, to the river.
The calculation assumes dilution by the, flow of Circulating Water(360000 gpm) occurring concurrently with this discharge.
APPLICABLE LIMITS.' LIQUID"RELEASE CalculatedValue TECHNICAL SPECIFICATIONS Liauid Effluents: Concentrations I)T.S.3.8.A.1 - 1 MPC as determined by 10CFR20, App.B, Table II, Col. 2..
conc. (Noble Gases excluded) 2.92E-3 MPC's 2)T.S.3.8.A.1 Total Noble Gases.
Conc. S 2E uci/cc . . 1.16E -9. ic i/cc Liquid Effluents: Dose 1)Total Body Dose -T.S.3.8.B.1 1.5 mrem in any quarter, 3 mrem total for year 1.52E-6 rnrem, 2)organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year' . 7.47E-4 mrem IOCFR5O.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.92E-34MPC's. .
NPDES REPORTING REQUIREMENTS Unplanned Releases *
- Yes iOCFR20 App B, Table II, Col.2
(< 1 MPC) 2.92E-3 MPC' Total Radionuclides(excluding tritium) shall be < 5 curies per year.
4.42E-4 curies Total Tritium shall be K 5 curies per year 4.82E-4 curies
.Dose.
Calendar quarter - < 1.5 mrem total body 1*52E-6 `rerm
-<5 mrem to-any organ 7.47E-4 mrem Calendar year < 3 mrem total body. 1.52E-6 mrem
- 10imrem to any organ, 7.:47E-4 mrem pH 6.5 to 8.5 Standard Units 7.6 Flow - 14.4 million' gallons per' day 12000 gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive Material(except tritium and dissolved noble gases < 1E-7 uci/m14 4. 1OE-9 uci/ml Additional action levels
>2% of IE-7(or 2E-9)uci/ml* 4.10E-9 uci/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health Within 14 days I. (see regulation for additional details).-
>4% of 1E-7(or 4E-9)uci/ml4 4.1i 0E-9 uci/ml Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
- 2. Tritium -
- 3E-3 uci/ml 5.772E-9 uci/ml (see regulation for additional quarterly limits)
Dissolved noble gases- < 4E-5 uci/ml. , 1.1.6E-9 uci/xm1
.(see regulation for additional quarterly limits)
AA; A4
SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92. :.
Bases - The "Calculated Value is based upon the asSumnption thaft :
12000 gallons of radioactive water was pumped out 'of the TB Clean"'.:
Sump and discharged, through the normal flow.path," to the river..
The. calculation assumes dilution
- by..the flow . of.'Circulating Water(360000 gpm) occurring concurrently with this discharge.:"".
- APPLICABLE LIMITS * " " ", ". LIQUID .RELEASE ; :
- . - "':. ..": ,- ,...Ca culatedVal'ie'.
TECHNICAL SPECIFICATIONS .
S"Liquid Effluents: Concentrations 1)T.S.3.8.A.l --S 1 MPC as determined
-by 10CFR20, App.B, Table II, Col..2 conc.(Noble Gases excluded) .. 2'92E-3 MPC s"
- "" 2)T.S.3.8.A.1 - Total Noble Gases .".
Conc. S 2E-4 uci/cc ' 1.16E-9 uci/cdc Liquid Effluents: Dose 1)Total Body Dose -T.s.3.8.B.I 1.5 mrem in any quarter, 3.mrem total for year .1.52E-6 mrem 2)Organ Dose - T.S.3.8.B.1 -
5mrem in any quarter,
.10 mrem total for year 7.47E-4 mrem 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.92E-3 MPC's NPDES REPORTING REQUIREMENTS Unplanned Releases . ."Yes' 10CFR20 App B,.Table -II, Col.2 (1 MPC) .- 2.92E-3 MPCS' Total Radionuclides(excluding tritium) . ..
shall be S 5. curies per year . 4.42E,4 -... curies per. ~ ~ 4.4.2 Total Tritium shall be S 5 curies peryear : 4.82E-4 'curies
- Dose :
Calendar quarter - . 1.5.mrem total body.....";52E6"mre
- < 5 mre"'to- any organ. 7.47E-4 mrem alendrmre 3 total bodyy* :..h 1.52E 6 mtrerm.
10 mrem to any organ 1 7 47E 4 mrem.
pH
- 6.5 to 8.5 Standard Unxts 7.6 Fi w' 14.
Flow- 14.4. mi l o gal million gallons per day * **.12000
.0***.i:*
. gallons'
- VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive Material(except tritium and dissolved noble gases 1E-7 uci/m14 1 4.10E-9guci/ml Additional action levels 4
>2% of IE-7(or 2E-9)uci/ml. 4.10E-9 u~ci'/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days (see regulation for additional details)
>4% of lE-7(or 4E-9)uci/ml4 . 4.10E-9 uci/mi SRequires investigation, immediate report to the Vt. Board of Health and then, < 14days later,-
i
- ... : *". followup report to Vt. Board of Health(see regulation for additional
- details)..
- 3. Dissolved noble gases -
- 4E-5 uci/mi 1.16E-9 uci/ml (see regulation for-.additional quarterly limits)
L 46E. 44A.~.44 "kV 4dd/ F) z nnc~' ~
p ** . *
SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases - The "Calculated Value is based.upon the* assumption that 12000 gallons of radioactive water, was pumped out."f the TB Clean Sump and discharged, through the normal flw .path, to the river'..
The calculation . assumes dilution by the ;.flow .bf *Circulating Water(360000 gpm) occurring concurrently with this discharge:.:.. "
APPLICABLE LIMITS * . : . . .
.* .... "'.LIQUID RELEASE CalculatedValuei-i TECHNICAL SPECIFICATIONS .
Liquid Effluents: Concentrations 1IT..S.3.8.A.1 - < 1 MPC as determined "
'by 10CFR2O, App.B, Table.II, Col. 2. " . 2.92E-3 MPC's conc. (Noble Gases excluded) 2)T.S.3.8.A.1- Total Noble Gases Conc. S 2E-4 uci/cc- ' 1.16E-9 uci/cc Liquid Effluents: Dose 1)Total Body Dose -T.S.3.8.B.l 1.5 mrem in any quarter, 3 mrem total for year 1.52E-6 mrem 2)Organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year 7.417E-4 mrem 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.92E-3 MPC's NPDES REPORTING REQUIREMENTS Unplanned Releases *i * *. Yes.
10CFR20 App B, Table II, Col.2 . .
92E-. PCs
. ( 1MPC) . . . . . . E-3 Total Radionuclides(excluding' tritium) .
shall be e 5 curies per. year. 4.42E-4 curies.
- ... .Total Tritium shall be 55 curies per year ""4.82E-4 ries; Dose..
Calendar quarter -K 1.5 mrem.total, o'dy * .
52E-6 mrem
- 55 rem"to-aiiy organ 7 -47E-4 nirem`-
Calendar yearter 3 ir-em total0body"-.'52E-6 mrem 10 mrem to any organ 1- 'h 7.-47E-4 mrem pH . 6.5 to 8.5 Standard Units 7.6
. Flow - 14.4 million gallons per day 12000 gallons*
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)-
- 1. Radioactive Material(except tritium and dissolved noble, gases S 1E-7 uci/m14 . * - 4.10E-9 uci/mi Additional action levels
>2% of lE-7(or 2E-9)uci/ml. 4.IOE-9 uci/ml Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days :J (see regulation for additional details)
>4% of 1E-7(or 4E-9)ubi/m14 4.1oE-9 uci/ml Requires investigation,.
immediate report to the Vt. Board of Health and then, < 14days later,..
followup report to Vt. Board of Health(see regulation for additional.
details)
.
- 5.72E-9 uci/ml (see regulation for additional quarterly limits)
- 3. Dissolved noble gases - < 4E-5 uci/ml 1.16E-9 uci/ml (see regulation for additional quarterly
- .. limits)
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OPERATIONS DEPARTMENT MEMORANDUM TO: S.Skibniowsky DATE:8/18/92 FROM: J.T.Herron FILE:
SUBJECT:
Condensate spill On- 8/14/92 R. Gerdus and I needed to evaluate if the notification requirements of 10CFR50.72 had been met which would require us to contact the NRC via the NRC red phone. In order to make the determination with respect to the applicable release limits we assumed that 12000 gallons of water was pumped out of the clean sump to the circ water discharge block. This is an extremely conservative value in that the we assumed one hour of continuous sump pump operation at the capacity of the pump @ 200 gpm.
After further review, a more realistic value of the amount of water discharged from the sump to the circ water discharge block would be @ 1000 gallons. This is, in my opinion, still very conservative in that at no time during the spill had the water reached the sump enclosure. Operation personnel, in the area at the time of the spill, have stated that the only source of contamination believed to have migrated to the sump was from the floor drains. It is our belief that the floor drain plugs, that are present to prevent the intrusion of contamination into the clean sump, were not water tight. The conservative 1000 gallons figure was based on the following.
1- The TBCCW clean sump pump timer readings have shown an average of @ 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of operation per week over the past month.
2- Based on #1 above the TBCCW clean sump pumps operate @ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per day which. in turn correlate to 1 pump down per hour.
3- The sump volume is @500 gal.
4- Since the event went on for @ 45 min. a conservative approach of 2 pump downs in the 45 min. would be appropriate.
5- The float system in the sump is set up to pump @ half-.of the tank volume or.@ 250 gallons.
In conclusion I would concur with your assumption to use 1000 gallons of radioactive water to calculate the liquid release values for the 8/14/92 liquid release.
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EVRLUATION OF TBCCW SUMP RELEASE PATHWAY - 8/14/92 Calculations Assumptions The TBCCW sump pump is rated at 200 gpm. The worst case scenario is that this sump ran for one hour while radioactive liquid from the backwash receiving tank was overflowing onto the floor and leaking into the sump.-
The one hour duration was based upon the fact that the SW rad monitýor alarm came in high at 1338 and the TBCCW clean sump was secured at 1430.
Chemistry technicians sampled the clean sump at 1410 and the TBCCW area floor at 1405. Isotopic analyses of both the floor and the sump are attached. A tritium analysis was performed on the sump sample and found to be 1.06E-5 uci/ml at 1410..
- . 3Only 1 4euir radionuclides were identified in the 'clean sump(I-"
1311A 1-133, 1-134 and 1-135) probably due to the shorter count time of this sample. Therefore, the floor sample data was used to extrapolate the probable concentrations of all identified radionuclides possible in'the sump sample. This ratio was set at 600 to 1 based upon the worst case radioiodine r4tio.
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- 5 cc- x x. .. A .L . * ;Lý.. ..
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TOTAL BODY AND MAXIMUM ORGAN DOSES FROM LIQUID RADWASTE RELEASES SoR \LOOO 5\ * -MONTH__ YEAR_ _
(2A) Max..organ (213) curies Total Body %Ro.m Released X Dose Factor = innem: (then Ci) X Dose Factor Radionuclide 2.06E-04' .X 2.06E-64 _________R H-3 q.L C-q X 3*38E-02 X 3,38E-02
= ___ ____
Na-24 X 3. lOE-04 X. 6.96E-02 =
= __ ____
Cr-51 x 2# 08E-O01'. X 3. OOE+OO _______
Mn-54 6 x 8.53E-06 Mn-56 X,.ý.5.29H-03 X 2.49E-01 = X 1484E+00 ______
Fe-59 x 5. 97E-;02 4.34E-61
= X ______
Co-58 X 2 *13E-01. X 1. 28E+00
- ______
Co-60 X 8.06E+00 = X 1. 64E+01 ______
- Zn-64 X 2 *5SE-01 X 8.91E+00
= ______
Sr-89 (1) X 4.23E+01 1. 67E+02
= X ______
Sr-90 (1) X 4.21E-04. 1636Eý-01
= X __ ____
Zr-95 X 4.51E-02'. ______=_
- x 4.79E-03 S.04E-06 X 2.33E-04 ¶ \-5E-1cJ F'~'
To-99m 2.22E-01
- 8.44E-03' X _____
Sb-124 ~ X 2.57E-02 X 1.47E+01 - .~,F-L4
.1-131 t. r- F-72
- j. lOE-06 = X 1.29E-04 ~ -35~
1-132 1-133 X 3.31E-03 = *X 1. 63E+00 _ ____ rz ___
= X 5'90E-02 PI.s .C 1-135 ~ X 3.16E-04 *X 1. 60E+02 __ _____
Cs-134 1.28E+02 Cs-137 I A..V_; Ca X 7. 58E+01. X 1421E+02 ______
X 9M7E-02 V___
___6 Ba-140 X 4.08BE-03 2.31E-05 X 4.10E-02 __ _ _ _ _
Ce-141 X 8.90E+00 1418E-02 = _______
W-187 D (SUM) -q wr D lq :, (SUH) tb mRem (3A) MO. mRem(3B)
(2B) T.S. 368.B.1.Limits:
(1) Use most recent data available for Sr-89 and Sr-90. 5 mRem in any quarter, (2A) T.S. 3.8.B.1 Limits:. 1.5.mRem in any quarter, 10 mRem per year.
3.0 mRem per year. (See also 3.8*C.1 and 3.8.M.l.)
(3A) ODCM EQ 3-1. (3B) ODCM EQ 3-3 Reviewed By, VYOPF 4609.01 OP 4609 Rev. 8 Page I of 1 RT No. llFO16163
1L (,
%13.q (D SE,(0.
.... ~ .1. ,*
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Co60 Pu239 analyzed Calculated Value Scaling Scaling ISOT value expon. uCi/g MDA Used Factor Factor W e Demin Resin Data Co6O 73 1E-05 7.300E-04 5.60E-04 7.300E-04 I.OOOE+00 14 IE-06 4.500E-05 2.90E-05 4.500E-05 6.164E-02 FeSS 503 -06 5.030E-04 5.10E-05 5.030E-04 6.890E-01 N159 -36 lE- -3.600E-06 2.20E-05 2.200E-05 3.014E-02 Ni63 376 IE-06 .7760E-04 1 .20E-04 3.760E-04 5.151E-01 Pu238 1 IE-07 1. OOEE-07 4.SOE-06 4.500E-06 6.164E-03 1.25E+00 Pu239 19 1E-07 1.900 06 3.60E-06 3.600E-06 4.932E-03 1.OOE+0O Pu241 55 1E-06 5.500E-O 1.90E-04 1.900E-04 2.603E-01 5.28E+/-01.
Am241 46 1E-07 4.600E-06 ""..30E-06 5.300E-06 7.260E-03 1 .47E+00 Cm242 4 1E-07 4.OOOE-07 3.8" 3.8OOE-06 5.205E-03 1.06E+00 Cm244 -68 1E-09 -6.800E-08 2.601 2.600E-06 3.562E-03 7.22E-01 Np237 -24 1E-06 -2.400E-05 7 .808E-02 1.58E+01 Cs Scal in Sactor Cs137 595 1E-65 5.'950E-03 5.00E-04 5.950E-03 1.00 +00 Sr9o 134 1E-07 1.340E-'05 1.40E-05 1.400E-05 2.353E-Tc99 -36 1E-07 -3.600E-06 8.00E-06 8.OOOE-06 1.345E-03 1129 8 IE-07 8.000E-07 1.20E-05 1 .200E-05 2.017E-03 Condemin Resin Data(Avg of A & e)
Co60 751 IE-03 7.510E-01 6.ISE-01 7.510E-01 1.OOOE+00 C 14 111.5 IE-05 1.115E-03 3.95E-04 1.115E-03 1.485E-03 Fe5S 408.5 1E-03 4.085E-01 4.25E-03 4.085E-01 5.439E-01 Ni59 -1 IE-05 -1.000E-05 1.55E-03 1.550E-03 2.064E-03 Ni63 1552 1E-04 1.552E-01 8.85E-03 1.552E-01 2.067E-01 Pu238 15 1E-06 1.500E-05 3.S5E-05 3.550E-05 4.727E-05 1 .39E+00 Pu239 32.5 1E-07 3.250E-06 2 .55E-05 2.550E-05 3.395E-05 1.OOE+O0 Pu241383.5 1E-04 3.835E-02 2.OOE-02 3.835E-02 5.107E-02 1 .50E+03 Am241 9 1E-06 9.OOOE-06 5.45E-05 5.450E-05 7.257E-05 2.14E+00 Cm242 54 1E-07 5.400E-06 2 .80E-05 2.800E-05 3.728E-05 1.10E+00 Cm244 17.8 1E-07 1.780E-06 2.35E-05 2.350E-05 3.129E-05 9.22E-01 Np237-183. 1E-06 -1.835E-04 5.05E-04 5.050E-04 6.724E-04 1.48E+01 J Cs Scaling Factor Cs137 397 1E-03 3.970E-01 6.SOE..02 3.970E-01 I.OooE+O0 Sr9o 314.5 IE-04 3.145E-02 2.55E-03 3.145E-02 7.922E-02 Tc99 -4 IE-04 -4.OOOE-04 4.75E-03 4.750E-03 1 .196E-02 1129 2 1E-05 2 .OOOE-05 4.50E-04 4.500E-04 1.134E-03 G- '69 3-7 -7.5 1 r,- - -3 S.-7-75 E ýj 5.0 t-,3 Ok.500\Vt I
- °.
MAILED AP:3019e YANKEE ATOIXC ILECTRIC COIPANY ENVIRONrNLTAL LABORATORY 10 CFX Part 50/61 Analysis RePOrt Page 1 of 2 Laboratory tSepte Numler: 203032# Customer: Vermiont Yankee Sempts Sul:mfssion Codes VRES0580992 si$ple Reference Data: February 26, 1992 Media Typez Resin Date Splpe Received: March 5. 1992 Total Amt of "tol Senti 0.11 a Report Date: April 29, 1992 Sa"to Description; NHO Condensate Rosin Atiquot Activity Concentration Detectable Concentration (A)
Weight I 10 Overall on Refertnce Date
'Analysis Processed Analysis . Elci/vl Date on Reference CALCULATED REQUIRED WIt/0) EALW] Notecs)
Requested [a] Date H-3 9 .600E*04 04/03/92 C 29 2 29 )E-04 49 E-04 4,0E-01 C- 14 ¶.2?00E-02 *03128/92 C 149 i 19 )E-05 45 E-05 8.0E-02 e Fe-55 2.1000f-03 03/18/92 C 421
- 35 )E403 40 e-04 7.OE+O0 B 15 2.2E+00 C 111-59 a.4DOOE-04 03/27/92 C -23 e 41 )E05 E-04 3.5e-02 S 111-63 I .OOOOE-03 03/23/92 C 222
- 19 )E-03 88 E-04
.3 Sr-89 2.1000E-03 04/02/92 C 565 43 )E-03 4 52 E-04 Sr*90 2. 1000e-03 04/02/9Z C 202 a 19')E-04 21 E-04 4.OE-D4 Ic-99 9.200of-04 04/23/PZ ( -9 A 17 )E-04 57 E-04 3.OE-02 up-237 2.12002-03 03/18/92 C -176 t 82 )E-06 &.* E-05 I.0E-03 B Pu-238 2.11 OOE-03 03/17/92 C 13
- 21 )E-06 51 E-06 I.0E-03 Pu-239,240 2.11002-03 03/17/92 C -39 a 22 )E-D7 33 E-06 1.0E-03 Pu-241 4.90OOE-D4 0,4/07/92 C 726 1 70.)E-04 11 E-03 3.5E-02 Am-241 2.1100E-03 03/16/92 C 10 t*16 )E-06 56 E-06 1.0E-03 Ciu-242 2.11002-031 - 03116/92 C 124 1 95 )E*07 21 E-06 2.OE-01 Czu-243,244 2.1100E-03 03/16/92 C 48
- 62 )E-07 21 E-06 1.0E-03 1-129 6.50002-03 04/13/92 C 9 t 13 )9-05 53 E-05 B.OE-04 Note*s): 1-A -Calculated NDCs are a-postoriorl values.
2 - Results are statistically positive at the 99.9% confidence level (activity it greeter then three tlmes the standard deviation).
C - Requireid MOC is for activated metal.
Rev*ewed by
-.- e E. K.l4)reno Jsfýei aeC.uryC. kurray
- - Updated to include all requested 10 CFR analyses.
e .'IP a,
MAILED APR 301 YANUE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY 10 CFR Part 50161 Analysis keort
...... m..........................
Pace 2 of 2 Laboratory emple Nurber: .Z03032 Customer: Vermont Yankee
&a"leSubmission Code: VRE905* 092 Sample Reference Date: february 26, 1992 Medl Type: Resin Date $ample Received: Marc 5, 199M Total Amt of smvlte Sent: 0.11 g Cotrit Date: March 9, 1992 Report Datat AprIl 29, 1992 Sample
Description:
"30 Corgle*ata ResIn
. Miniffum Al iquot Activity Concentration Detectable Concentration (A)
Iguight. i 1r Overall on Reference Date Antalysi Processed on Reference Date CALCULATED REQUIRED Requested (91 Isotope [AC$ltl [ECI/9) [ACI/03 Note(s)
Gaam Scan 0.0424 Cr--1 C 12 a 21 )E-02 85 E-02 Nn-54 125 a 19 )E-03 61 E-03, - 7.OE*00 Co-57 (. 13 23 )E-03 89 E.03 7.0E÷DO Co-38 C -27 +/- 25 )E-03 10 E-02 7I.DE+00 Fe-59 ( -50 a54 )E-03 23 E-0Z ?.OE*00 Co-60 C 946 a 54 )E-03 67 E-03 B
( B Zn-65 1p86 82 )E-03 17 '-02 7.OE+00.
Nb-94 .44 25 )E-03 11 E-02 2.0E-03 C Zr-95 -6 38 )E-03 16 E-02 7.OE+00 Rb-95 ( 12 a 25 )E-03 10 E-02 7.02+00
( 90 E-03 7. 0E÷00 Ru-i03 18 a 22 )E-03 Ru-106 C *6 +/- 19 )E-03 79 E-02 Ag-1OBM ( 5 a 19 )E-03 77 E-03 7.0E+00 C 14 E-02 7.0E.00 7.OE.0O AV-110m 34 33 )E-03 Sb-124 29 23 )E-03 B4 E-03 7.0E+00 7f.0E+00 Sb-125 4 t 58 )E-03 24 E-02 CO-134 ( 3S0 k 24 75 E-03 7.W+00 B Cs -137 ( 995 a 59 )E-03 75 E-03 I.OE-02 on-140 ( 8 i 14 56 E-02 La-140 ( 334 a 38 13 E-02 L B
( 21 E-02 74OE+O0 Ce-i141 62 a 55 )E-03 7OE÷00 Ce-144 ( -50 a 19 )E-02 72 E-02 Not*Cs):
A - Calculated MDCs are &-posterlorl values.
- Results are statistialley positive at the 99.9% confidence level Cactivlty Is greater than three times the standard deviation).
C - Re*tred HOC is for activated mmtal. S Reviewed by a
E. M.1 reno Jamee C. kurray
. MAILED YANIKEE ATCHIC ELECTRIC COMIPANY ENVIROUMENTAL LANORATORY 10 CFR Part 50/61 Anatysis Report g..........
Paeg I of 2 Customer: Vermont Yankee Laboratory Sample Number: Z03031 VRES05AO992 supl. Reference Oato' February 26, 1992 Sample Sukalmslon Codet media Type: Resin Date Sarmple Received: March 5, 1992 0.174 g Report Watei April 29, 1992 Total Amt tf Iapte Sent:
Sanple Descriptlon: CONDENSATE RESIN "Au Niniui Aliquat Activity Concentration Detectable Concentration (A)
Weight i iv Overatt on Reference Date Anlysis on Reference Date CALCULATED REQUIRED Analysis Processed
(*ci/Is rtcvisg (5CI//fI NoteCs)
Requcsted tg) Date C 31 1 10 )E-04 17 E-04 4.0E-01 B H-3 1.4200E-03 04/10/92 8.08-02 C-14 03/28/92 74 t 13 )E-05 34 E-05 9 1.6600(-02 U 1.9600E-03 03/18/92 C 396 1 33 )E-03 45 E-04 7.0t0DO Fe-55 C 7.7OOOE-04 03/25/92 C 21 k 47 )E-05 16 E*04 2.ZE+00 H1-59 B 1.000OE,03 03/23/92 C 884 1 82 )E-04 89 E-04 3.5E-02 NI-63 1.9600D-03 04/02/92 C 190 t 13 KE-03 56 E-04 S Sr-B9 i.9600E-03 04/02192 C 427 1 32 )E-04 30 E-04 4.0f-04 Sr-90 04/23/92 C I 1 12 A8-04 38 E-04 3.CE-02 Tc-99 1.37OOE-03 C -191 1 90 )E*06 53 E-05 1.0E-03 Np-2 3 7 1.9eaGE-03 03/18/92 1.96002-03" 03/17/92 C Ir+/- .10 )E-06 20 E-06 1.0E-03 Pu-238 1.9600E-03 03f17/92 C 115 1 80 )E-07 18 E-06 10E-03 Pu-239,z40 Pu-241 6.50001-04 04/07/92 C 411 29 )E-04 91 E-04 3.5E-02 1.9600E-03 03/16/92 C B 1 17 )E-06 53 E-06 1.0E-03 Am-24,1 1.9600E-03 03/16/92 C -16 1 90 )E-07 35 E-06 2.0E-01 Cm-242 Cm-243,244 1.9600E-03 03/16/92 C -125 - 89 )E-08 26 E-06 1.OE-03 1.08008-02 04/10/92 C 101 +/-171 )E-06 29 E-05 .8.0-04 1-129 Note(s):
A - Calculated M4Cs are a-posteriori values.'
greater then three times 8 - Results are statisticalty positive at the 99.9t confidence level (activity to the standard deviation).
C - Rauired MFC Is for activated metal.
Reviewed by M oreio
- Updated to include all requested 20 CFR 61 analyses.
MAILED YANKEE ATOMIC ELECTRIC COMPANY ENVIRONXENTAL LABORATORY APR 3,0 10 CFR Part 50161 Analysis Report Page 2 of 2 Laboratory sempte NWmr: Z03031 Custower: Vermort Yankee Sanzea Submtiseion Code: VRE$OSA0992 Smpte Reference Date: February 26, 1992 Media Types Resin Date SImpte Received: March 5, 1992 Total Amt of $aurpto Sent: 0.174 0 Count Date: March 9, 1992 Report Dates Aprit 29, 1992 Simple Description; CONDENSATE RESIN "A,"
....... - .. o......b .......
Al iquot Activity Concentration Detectable Concentration (A) "
welght A lc OveralL on Reference Date Analysis Processed an Reference Date CALCULATED REDUIRED Requested Isotope ;CLi/g1 ElxCI/9 ci/9Cll Note(s)
Camme scan 0.0387 Cr-51 C 3 8 17 )E-02 67 E-02 Mn-54 ( 86 a 15 )E-03 52 S-03.1 7.OE+O0 9 Co-57 C -4 15 )E-03 59 E-03 7.0E+O0 Co-58 C -29 a 20 )E-03 84 E-03 7.OE+00 Fe-59 C B 42 )E-03 18 e-oz 7.OE+00 CO-60 C 556 a 33 )E-03 56 E-03 7.OE+00 B C )E-03 15 E-02 B Zn-65 432, 48 C )E-03 74 E-03 2.OE-03 C Nb-94 -1 18 Zr-95 C 15
- 29 )E-03 12 E-02 7.OE+O0 Nhb-95 C -11 a 21 )E-03 90 E-03 7.OE!O0.
.Ru-103 C 16 17 )E-03 67 E-03 7.0E100 C 7.0i*00O RU-106 *0 a 15 )!-02 60 E'0Z Ag-liom C -12 a 15 )E-03 60 E-03 7.6f+00
( 7.09+00
-60 a 27 )E-03 12 E.02 5b-124 C 43 a 21 )E-03 84 E-03 7.0f+DO sb-'125 C -35 45 KE-03 18 Eý-02 7.OE+00 Ca-134 C 58 E-03 7.OE00 B 166 a 14 )E-03 C i.OE-OZ II Cg-137 4" 30 )E-03 55 E-03 sa-140 C 23 a 10 )E-02 39 E-0Z Le-140 C 220 a 30 )E-03 14 E-0Z B Ce-141 C 71 a 35 )E-03 14fE-02 7.0E400 CS-144 -23 1 12 )E-02 47 E-02 7.VE+00
....... ... ...... ......... ,.......,........ ....- ;ý........
'. ....... °. ..... o...............o........T..........* ........ °..........
Note~s):
A - Calculated MD C are a-poaterlorl values.
5 - Results are statisticalty positive at the 99.9% confidence level (activity Is greater than~three time the standard deviation).
C - Required HOC to for activated owtal.
Reviewed by Eorenfo
,91James C. Mu~rra 7
MEMORANDUM To: Distribution September 8, 1992 From: D. Voland Vernon
Subject:
Offsite Dose Calculations - August 1992 Attached is a copy of the offsite doses calculated for the month of August 1992. If you have any questions concerning this information, please contact me at your earliest convenience.
copy with attachments:
J.T. Herron R.D. Pagodin J.T. McCarthy S.P. Skibniowsky M.S. Strum (YNSD-Bolton)
G.D. Weyman Chemistry Correspondence Files Chemistry Completed Forms Files
IN TOTAL BODY AND MAXIMUM ORGAN DOSES FROM LIQUID RADWASTE RELEASES MONTH AUG.
YEAR 1992 Curies Total Body (2A) Max. Organ (2B)
Radionuclide Released X Dose Factor = mRem: (then Ci) X Dose Factor mRem 4.02E-5 X 2.06E-04 8.28E-9 X 2.06E-04 = 8.28E-9 H-3 -
Na-24 X 3.38E-02. X 3.38E-02 Cr-51i X 3. 1OE-04 X 6.96E-02 Mn-54. x 2.08E-O1 X.3.OOE+00 Mn-56 x 8.53E-06 X 5.29E-03 Fe-59 2.49E-01 X 1.84E+00 Co-58 xX 5.97E-02 X 4.34E-01 Co-60 x 2.13E-O1 X 1.28E+00
.Zn-64 8.06E+00 X 1.64E+01
- Sr-89 (1) <2.14E-7 X 2.55E-01 - <5.46E-8 X 8.91E+00 - <1.91E-6 Sr-90 (1) <I. 78E-8 X 4.23E+01 = <7.53E X 1.67E+02 -. <2.97E-6 Zr-95 X 4.21E-04 X 1.36E-01 X X 4.51E-02 Mo-99 I.26E-7 X 4.79E-03 X 2.33E-04 2.94E-11 Tc-99m X 5.04E-06 =6.35E-13 -
X 2.22E-01 Sb-124 3.46E-6 X 8.44E-03 5.09E-5 8.89E-8 X 1.47E+01
<1.58E-6 X 2.57E-02 1-131 -
1-132 3.1OE-06 - 4.90E-12 X 1.29E-04 - 2.04E-10 1-133 6.63E-6 X 3.31E-03 2.19E-8 X 1.63E+00 - 1.08E-5 7.27E-6 X -
= 2.30E-9 X 5.90E-02 4.29E-7 X 3.16E-04 1-135 X 1.60E+02 Cs-134 X 1. 28E+02 X 1.21E+02 Cs-137 1. 17E-6 X 7.58E+01 1.14E-7 X 9.72E-02 2.39E-7 X 4.08E-03 4.77E-9 -
Ba-140 -
5.52E-12 X 4.10E-02 9.80E-9 X 2.31E-05 = -
- Ce-141 W-187 1.18E-02 X 8.90E+00
= (sUM) .<9,35E-7 Dr =. (SUM) = <6.72E-5 D -
tb mRem(3A) mo mRem(3B)
(1) Use most recent data available for Sr-89 and Sr-90. (2B) T.S. 3.8.B.1 Limits:
(2A) T.S. 3.8.B.1 Limits: 1.5 mRem in any quarter* 5 mRem in any quarter, 3.0 mRem per year. (See also 3.8.C.1 and 3.8.M.I.) 10 mRem.per year.
(3A) ODCM EQ 3-1. (3B) ODCM EQ 3-3 VYOPF 4609.01 Reviewed By OP 4609 Rev. 8 Page I of I RT. No. li.F01.163
BUILDING VENTILATION* YEAR 9 1992 BETA AND GAMMA AIR DOSES FROM NOBLE GASES - TURBINE (1A) Gamma (1B)
Curies . Beta TRad mRad: (then Ci) X Dose Factor =
Radionuclide Released X Dose Factor =
X 3.28E-3 11 X 9.30E-3 Ar-41 x 1.93t-5 Kr-83m X 2.88E-4
4.83E-5 x 1. 23E-3 = 3.O01E-5 Kr-85m 2.45E-2 X 1.97E-3 X 1.95E-3 x 1.72E-5 Kr-85 1.87E-3 x 6.17E-3 = 1.12R-3 Kr-87 1.81E-1 X 1.03E-2
= -2.70E-4 x 1. 52E-2 = 1.40E-3 Kr-88 9.23E-2 X 2.93E-3 1.l1E-3 x 1. 56E-4 Xe-131m X 1.48E-3 x 3.27E-4 Xe-133m X
= 1.08E-5 x 3.53E-4 = 3.62E-6 Xe-133 1.02E-2 X 1.05E-3
= 7.43E-4 x 3.3 6E-3 = 3.38E-3 Xe-135m 1.01E0 X 7.39E-4
3.62E-4 x 1.92E-3 = 2.83E-4 Xe-135 1.47E-1 X 2.46E-3 X L. 27E-2 x 1. 51E-3 Xe-137 2,07E-2 X 9.21E-3 = 4.02E-2 Xe-138 4.37E0. X 4.75E-3 D =0.55 X (SUM) 2.40E-2 ' D 0.13 X (SUM) 4.64E-2
airg airg 7
1.32E-2 D = 6.04E-3 D mRad(2B) airg mRad(2A) airg quarter, 20 mRad (IB) T.S.3.8.F.1 Limit = 5 mRad (IA) T.S.3.8.F.I Limit = 10 mRad any any quarter, 10 maRad per per year. year.
(2A) ODCM EQ 3-43. (2B) ODCM EQ 3-41.
VYOPF 4609.05 Reviewed By OP 4609 Rev. 8 Page I of 1 RT No. 11.F01.161
MEMORANDUM VERMONT YANKEE - VERNON To File Date October 14, 1992 From Deborah Voland Subject REVISION OF AUGUST 1992 DOSE CALCULATIONS Enclosed are 2 pages from the monthly dose calculations from August that have been revised. The revision of the "Beta and Gamma Air Doses from Noble Gases - Turbine Building Ventilation" was due to a minor error caused by unfamiliarity in using the spreadsheet designed to perform the calculation when the doses were calculated by someone filling in for me when I was on vacation. The other revision is the result of calculating values for Sr-89 and Sr-90 for the liquid release that occurred in August. The values were derived from the LLD levels of the. Turbine Sump sample and the scaling factors typical in the associated waste stream.
pee. I-EV4LUATION OF TBCCW SUMP RELEASE PATHWAY - 8/14/92 .
Calculations Assumptions The TBCCW sump pump is rated at 200.;gpm. The "worst'-case'.
scenario is that this sump ran for One hour while radioactive' liquid from the backwash receiving tank was overflowing-onto the floor and leaking into the sump. . ..-.. U-.:
The one hour duration Was based upon the fact tat the"'Sw rad monitor alarm came in high at 1338 and the. TBCCW clean sump was secured at 1430.-
" hemistry technicians sampled the clean sump at 1410 and the.
-TBCCW area floor at 1405. Isotopic analyses of both the floor and the sump are attached. *A tritium analysis was performed on the sump sample and found to be 1.06E-5 uci/ml at 1410.:
Lo.nly fOeikyradionuclides, were identified in the clean sump(I-
. 31, 1-133, 1-134 and 1-135) probabl due to the shorter count time 1
of this sample. Therefore, the floor sample *data was used. to extrapolate the probable concentrations of all.. identified radionuclides possible in the sump sample. This ratiowas set at.
600 to 1 based upon the worst case radioiodine.ratio.
( :
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lID RADWASTE RELEJ TOTAL BODY AND MAXIMUH ORGAN DOSES FROM LTQE MONTH -____
YEAR____
.*Max..Organ *(213) cureos 'Total Body (2A)
Released x Dose Factor - **ef* (then Ci) X Dose Factor Radionuallde X 2.06E-04
' H-3 2.06E-04 X 3.38E-02
_______X.
Nra-24* 3 .38E-02
____ ___X 3 .10E-04 X:6*.96E-02 Cr-51 ___ x
- X 3.OOE+00 Mn-54 2 *OE-01
____ ___ X 80.53E-06 X..5.29E-03 Mn-56 X X 1684E+00
- Fe-59.. ____
2.*49E-ý01 X 4.34E-O1 Co-58 5,97E-02. X 1.28E+00 co-.60" 2.13H-01. X 1.64E+01 Zn-64 8,06H+PO 2_ _ _ _ _
X 8.91E+00 =9 Sr-89 (1 L 2.55E-01. 2,- 1.67E+02 4,23E+01 X Sr-90 (1 X 1.36E-01 4.21E-64 =E Zr-95 X 4.51E-02 N0-99 ____ x 4.79E-03 X 2.33E-04 10 To-99m 5. .049-ý06 X 2,22E-01 Sb-124 8.44E-03* !6t nmE 1.47E+01
~ X 2 *57E-02 X m t . paL 1-131 X 1.29E-04 1-132 A4 jEF5.L.5. X 3, IOE-06 X 1.63E+00 3.31E-03 z=
1-133 X 5.90E-02 X"135 V;_ X 3.16E-04 n*
X 1.60E+02 C--134 1,28E+02 X 1.21E+02' Co-137 7.58E+01 IN __ _ X X 9i72E-02 Ba-140 4.0GE-;03 2.31E-05 X 4.10E-02 Ce-141 X 8.90E+00 W-187: 1.1OE-02
- q. (SUM) in . Dliq (SUH) 13tb.' mo
- mnRem (3B) mnhem (3 A)
(1) Use most recent data available for Sr-89 and Sr-90.. (213) t T.S. 3.8.B.1.Limits:
5 mRem in any quarter, (2A) T,S. 3.8.B1. Limits:.. 1.5, mRem*in any quarter, 10 aRemeper year.
. ... 3.0 mRem.per..year. (See also.3.8,C.1 and 3.8.M.1.)
- * (3B). ODCH EQ 3-3"
.. (3A) ODC, ..EQ.3--1.
Reviewed By VYOPF 469 " .01 OP 4609 Rev. 8":'.*.'. '
- Page,1. of 1 RT No. 11.F01.163.
14-AUG-92 15:01:15 VERMONT YANKEE NUCLEAR POWER CORPORATION or- Svc,\ki x.5i SAMPLE DA1E ......... . 14-AUG-92 14:10:00 SAMPLE IDENTIFICATION: TB CLEAN SUMP
- LIQUID MARINELLI C-0 TYPE OF SAMPLE .......
SAMPLE QUANTITY ...... : 1000.000 UNITS: ML SAMPLE GEOMETRY...... : VY2005 OPERATOR ............ : SCM EFFICIENCY FILE NAME.: EFF.VY2005,,
ACQUIRE DATE: 14-AUG-92 14:24:21. *.FWHM(1332) 1.867 PRESET TIME(ýIVE):. 2000..SEC
- SENSITIVITY: 5.000 ELAPSED REAL'TIME: 2001. SEC
- SHAPE-PARAMETER : 10.0 %
ELAPSED LIVE:,TIME: 2000. SEC
- NBR ITERATIONS: 10.
DETECTOR..:. 20% HPGE .* LIBRARY NUCL .LIBl CALIB DATE: .14-AUG-ý92'00:56:29 *.ENERGY TOLERANCE 1.500KV
- KEV/CHNL..: 0.5001629
- HALF LIFE RATIO 8.00 OFFSET..... :*-0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q.:COEFF..: O.O00E-O1 KEV/C**2
- DECAY TIME (MIN). 14.0:
ENERGY WINDOW .24.*90 TO 2048.56
.1.00-SIGMA %ERR
- PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW" CTS/SEC %ERR FIT
.1. 0 249.91 .264. 425. :1.21. .499.87 494 12 1.32E-01 17.3
- 2 0 284.07 71. 2-48. 1. 45 568.17 565 8 3.56E-02. 40.7 "0 364.45 826. 167.. 1. 26 728.88 724 9 4.13E-01 4.6 4 .0 417.86 86. 125. 835.67 829 12 4.28E-02 *.30.0
.50 511.04 3455. 168. 2.53 1021.96 1014 22 1.73E 00 2.0 158. ,54. 1.53 1052.88 1049 17 7.88E-02 10.8.1.. 36E 00 6 2 526.51 7 .2 529.91 1239. 45. 1.33 .1059.68 1049 17 6.19E-01 3.0 8 0 546. 81 84. 43. 1.49 1093.49 1089 12 4.20E-02 20.2.
9 0 637.41 37. 38. 1.27 1274.62 1268 10 1.86E-02 38.0 10 0. 667.81 240. 37. 1.53 1335.40 1329 15.1.20E 9.0 11 0 772.69 .146. 16. 1.75' 1545.09 .1538 13*.7.28E-02 11.5 12 0.. 836.86 53. AZ. -2.11 1673.38 1668 11A2.65E-02 24.3 i1 *0 847.23 61. 52. 1. I1 1694.12 1687 14 3.03E-02 '27.2 14-.0 875.46 58. 18. 1.32 1750.57 1743. 15 2.90E-02 20.8 15 0 884.18 62. 19. 1.01 1768.00 1763 11 3.08E-02 20.8 16 .0 953.99 30. 18. 1.74 1907.56 19"02 11 1.50E-02 .40.4 17 0 1038.59 76. 26- 1.87 2076.71 2069- 17 3.80E-02 20.6 18 0- 1131.46 132.. 9. 1.70 2262.40 2258 10 6.58E-02 .10.1 195. 4. 1.51 2519.99 2511: 18 9.73E-02 8.0 19 0 1260. 30
- 13.: '9. 10 6.52E-03 52.6 20 0- 1298.49 1.42 2596.36 2592
- 80. 0. *2.44 2914.40 2905 22 4.OOE-02. 13.1 21 0 1457.57 22 0 1677.60 50. 0. 1.86 3354'. 32 3348 15 2.50E-02 14.1 23 0 1790.53 42. 4. '1.75 3580.10 3573 13 2.11E-02 .19.4 PEAK SEARCH COMPLETED (REV 15.7)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM 23 UNIDENTIFIED PEAKS 19 14 60.87%
IDENTIFIED IN
SUMMARY
REPORT FISSION GAS
.1,00-SIGMA 1.00-SIGMA NUCLIDE SBHR .HLIFE. DECAY UCI /UNIT ERROR %ERR XE-135 . FG 9. OH 1.040 2. 131E*-7 3.690E -8. .17.32 XE-135M FG 15. 65M 3.614 8.495E -7 9.141E -8 .10.76 FISSION PRODUCT 1.00-SIGMA. 1.00-SIGMA NUCLIDE SBHR
- HLIFE DECAY UCI /UNIT ERROR %ERR 1-131 FP 8.04D 1.002 9.131E -7
- 4.185E -8 4.58 1-132 :FP . 2. 30H .1.167 4.189E -7. 3.750E -8 8.95.
1-133 .FP 20. 80H 1.017 1.753E -6 5.285E -8. 3.02 1-134 FP 52. 60M 1.493. 2.799E -7 5.830E -8 ' 20.83 1-135 * "796
.FP 6.61H 1.056 1.920E -6 1.527E -7
14-AUG-92 14:20: 22 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DAYE .......... : 14-AUG-92 14:05:00 &4j~
SAMPLE IDENTIFICATION:. TB 222 SPILL TYPE OF SAMPLE ....... : 23ML'SCINT. VIAL 'e~-
SAMPLE QUANTITY ...... : 23.00000. UNITS: ML SAMPLE GEOMETRY ...... : VY2004 OPERATOR." .: GR
-EFFICIENCY FILE NAME.: EFF.VY2004 7, ACQUIRE DATE: 14-AUG-92 14:11:45
- FWHM(-1332) *1.867 PRESET TIME(IIVE): 500. SEC
- SENSITIVITY: 5.000 ELAPSED REAL'TIME: 508. SEC
- SHAPE PARAMETER 10.0 %
500. SEC NBR ITERATIONS: 10.
ELAPSED LIVE*-TIME:
- DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIB1.
CALIB*DATE: 14-AUG-92 00:56:04.'
- ENERGY TOLERANCE 1.500KV KEV/CHNL..: *0*5001629
- HALF LIFE RATIO* 8.00 OFFSET....: -0. 1059622 KEV
- ABUNDANCE LIMIT 80.00%.
Q." COEFF..: O.OOOE-01 KEV/C**2 *-DECAY TIME (MIN). 6.0 ENERGY WINDOW'. 24.90T0 2048 .56 1.00-SIGMA %ERR IT ENERGY AREA BKGND .FWHM CHANNEL*LEFT PW CTS/SEC. %ERR FIT 1 O* 80.30 1079. 3153. 1.52 160.75 155 12 2.16E 00 10.9 2 0 140.56 643. 2543. 0.94 281.24. 277. 9 1.29E00 14.7.
3 0 145.55 671. 1928. -1.13 291.21 *288 7 1.34E 00 11.6.
- 4. 6. 162.74 .372. 1985. 1.13 325.59 .322 15 7.44E-01 20.5 1.49E 00 5 6 165.88 1891. 1654. 1.04 331.86 322 15 3*78E 00 4.1 6 0 220.46 432. 2262. .1.15 440.98 437 8 8. 64E-01 19.5 7 0 249.77 4786. 2705. 1.12 499.59 .494 11 9.57E 00 2.6 5.284*. 27 752. 1685. 1.13 568.58 562 20.1.50E 00 9.7 6.33E-001 10 5 288.46 596. 1775. 1.12 576.94 562 20 1.19E 00 12.2 0 328.80 433. .2218. 1.00 657.60 :654 .8 8.66E-01 19.6 11 0 364.49 .8637. 2304. .1.19 .728.94 722 14 1.73E 01 .1.6 12 0 .417.86 563. 1040. 1.21 835.66 832 11/:1.13E 00 12.2 13 0 423.50 *156. 855.. 1.01 846.94 842 9 3.11E-01 34.4 14 0 434.28. 204. 1498. 4..49 868.48. 862 .16 4.08E-01 44.0 15 0 487.07. 933. 998. 1.27- '974.03. 968 13 1.87E 00 7.7 16 0 511.00 28700. 2006. 2.62 1021.88 1014 19'5.74E 01 0.7 17 2 522.60 399.* .414.. 1.29 -1045.07. 1042 24 7.98E-01 9.2. 1..78E 00 18 .. 3.1 2 526.62 2118. 599. 1.43 1053.11 1042 24:4'.24E 00" 0.9 2 .529.92 13207. 448. 1.31 1059.70 .1042 242.64E 01 20 0.. 537.21 537. 636. 1425. 1074.28 1069 11 1.07E'00 10.4 21 0 546.52 821. 464. .1.33 1092.90 1088 10 1.64E 00 6.2 0 555.57. .1134. .546. 1.30 1110.99 1105 12'2.27E'00 5.1 23 416. .1.39 0 595.47 .194. 1190.76 1186 10 3.87E-01 21.7
ENEERGY WINDOW . 24.90 TO 2048.56.
1.00-SIGMA %ERR PK IT. ENERGY AREA BKGND " FWHM 'CHANNEL LEFT PW. CTS/SEC %/ERR FIT 24 0 621.60 249. 579. 1.83 '1243.01 1237 13 4.98E-01 21.8 25 0 630.29 351. 595. 1.27 1260.38 1254 13 7.03E-01. 15.7 26 .0 637.08 355- 428. 1.40 .1273.95 1269 10 7.10E-01 12.6
.27 0 652.91 114. .344. 1.18 1305.61j 1303 7 2.28E-01 29.8
.28 .0. 667.67 2190. 792. 1.39 1335.12 1327 16 4..38E 00. 3.6
- 29. 7 677.47 93. 272. 1.21 1354.71 1351 13 1.85E-01 31.9 1. 53E 00
.30 .7 679.90 76. 291. 1.21 1359.58 1351 13' 1.51E-01 38.9
.31 0- 707.04. 251. 356. 1.75 1413.83 1409 11 5.03E-01 16.4
.32 o 722. 98 129. .330. 1.65 .1445.71 1440 11 2.57E-01 28.6
.33 0:o 728.08 101. .439. 4.73' 1455.90 1451 14 2.03E-01 45.6 34 0 749.T9. 469. .437. 1.66 1499.70 1494 15.9.38E-01 10.7
- 35 '314. :1.59 1545.05 1540 11 2.74E 00. 3.8 0 772.67 .1371.
"36 0 816.60 .262.' 378. 1.52 .1631.68 1628 11 5.24E-01 .. 15..9 37 O 836.ý91 502. .260., 1.64. 1673.49 1669 11 1.OOE.00 7.8 38 0 847.05 1290. 1.62 1693.77. 1685 .16'2.'58E 00 4.4
- 39 0 856.82 203.. .306. 1.69 1713.28 1707 13 4.06E-01. 19.4 40 0-875.28 477.. 286. ,1.60 *1750.21 1745 12 9.54E-01 8.7.
.. 41 0 884.26 836.. 306. 1.60 1768.15 1762 13 1.67E 00 5.8 42 0 925.78 -97.. 322*. 1.46 1851.17 1843 13 1.95E-01 -41.4' 0 954.31 350. *2:271. 1.95 1908.21 1900. 16- 6.99E01". 12.1 43
.44 0 973.39 136. 363. 3.37 1946.35 1940 15'2.71E-01 31.6.
45 0 1024.33 393. 232. 1.71 2048.20 2043. 12 7.86E-01 .9.8.
46 0 1038.71 552. 323. 1.85 2076.96 2068 15 1.10E 00 8.3 47 0 1072.91 150.-- 178. 1.63 2145.33 2139 1" 3.00E-01 20.6 "168. 189. 2.25 2202.78"2195 17 3.35E-01 22.3 48 0.1101.64 49 0 1123.98 220. 229. .1.34 2247.44 2240 15 4.40E-01. 17.5 50 2 1131.61 1273. 124. 1.75 2262.70-2257 21 2.55E 00 3.4 1.81E 00
.51 2 1136; 1 165. 127. 2.09 2271.69 2257 21.3.31E-01 .19.5 52 0.1237.85 200. 220. 5.48 2475.11 2463 "22-4.00E-01 21.5.
.53 0.1260.56 1670. S128.. 1.81 2520.50 2514 15 3.34E 00 2.9 54 0 1298.36 154. 165. 1.98 2596.09M2590 13 3.08E-01 19.6 55 0 1384.30 239. 91. 1.68 2767.91 2761 13-4i78E-01 10.5 56 0 1398.81 88. 69. 0.78 *2796.92 2793 10 1.76E-01 23.1 57 0 1457.50 440. 155.' 2.05 2914.27 2906 19 8.80E-01 . 8.4 58 0 1502.24 36. 77. 1.56 3003.72 2996 14 7.28E-02 54.5
.59* 0 1566.36 42. 53. 1.11 3131.90 3128 11 8.31E-02 36.6 60 0 .1596.33- 552. 38. 1.97 3191.84 3184 17 1.10E.00.. 5.0:
011 .0 1678.22 436. 42. 1..75 3355.57 3349 14,.S.71E-01 , 5.9
.62 0 1706.72 173. 33.. 1.52 3412.54 3405 16'3.46E-01 11.3 63 .0 1791.32 369, 11. 1.97 3581.69 3574 15 7.38E-01 5.9
- 21. 2.23 3615.05 3606 .18-9.16E-02 31.5 64 0 1808.01 46.
.65 .23. .5. 0.61 3661;87 3659 9 4.61E-02 33.1 0 1831.43 PEAK SEARCH COMPLETED (REV 15.7)
$MI.
- - -- .- -- -- . - -A -.
PAGE 1:
'SUMMrARY OFF NUCLIDE ACTIVITY TOTAL PEAKS IN SPECTRUM
.UNIDENTIFIED PEAKS 31 IDENTIFIEl IN
SUMMARY
REPORT 34 52.31%
FISSION GAS c.
1.00 -SIGMA 1.00-SIGMA 5-f NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-131M FG 11. 90D .1.000 5.739E -4 1.176E -4 20.50 XE-133 FG 5. 25D 10001 7.835E -5 8.57?E -6. 10.95 XE-135 FG 9. 08H 1.014 2.349E -4 6.013E -6 2.56 3.08 XE-135M FG A15. 65M 1.617 3.579E -4 *1.102E -5 FISSION PRODUCT 1.00-SIGMA 1. 00-SI GMA NUCLIDE SBHR HLIFE DECAY' *IUCI /UNIT ERROR %ERR TC-99M .FP .6.02H" 1.021 1.995E -5 2.934E -6 .14.71 1-131 FP 8.04D 1.001 6.398E -4 1.019E -5 S1.59 1-132 FP 2.30H 1.057
- 2.487E. -4 8.926E -6 3.59 1-133 FP 20.80H 1.006 1.296E -3 1.191E -5 0.92 1-134 FP *52.60M 1.155 2.216E -4 1.286E 5.81 1-135 FP 6.61H- .1.019 1.220E -3 3.537E -5 2.90 SR-91 FP 9.50H 1.013. 2.034E*-4 1.991E -5 9 .79 SR-92 FP 2.71H 1.048 *6.18SE -5 6.479E -6 10.47 Y-91M FP 49.71M 1.165 1.236E -4 6.291E -6 5.09 RU-106 FP 368.20D 1.000 2.509E -4 5.4Z8E -50 21.75 BA-139 FP 82.71M :1.096 3.536E -4 1. 458E -5 4.12 BA-140 .FP 12.79D 1.000 1.853E -4 1.934E -5 10.44 LA-140 FP 40.22H 1.003 1.473E -4 7.407E -6 5.'03 CE-141 FP 32.OOD 1.000 3.788E ;-5 4.407E -6 11.64
VPOTljNTIAL REPORT-Able OCCURiact oscrIiption 0t. o vent_ /condition / Pertinent Intarortion t Itnclude- cause it'knov and corrective actions takenj On August 14", 1992 at approximately. 1330 the ,condensate' demineralizer backwash receiving tank overflowed and covered the TBCCW area floor with radioactively contaminated water and resin to -
a level of 1-2 inches. A.sample taken from the clean sump'indicated the presence of statistically significant iodine activity. Since.
the sump pumps were on at the time, some of this activity'may'have'*
been discharged to the river. Operations was requested isolhte the ./
sump pumps; absorbent. material, was *placed around the dump to" originer: f.M prevent further contaminated material from getting into the sumpý :.
Splant c.nditions setoeting svsmt,: While an operator was backwashing the B condensate demineralizer and transfering to the condensate demineralizer backwash receiving tank, the pump 'which transfers water from the tank to radwaste
-failed.causing the backwash receivina tank to overflow.
ietificstiOem /'isviust (Ckhbe rall block* tkat apply)
ViC. Sia R staite other I morst N.otiicion Hsdo. [ CO iVeltd J Loa'Ratty*Made I - 4 moti f I Corp. Respeosibility I " Resident lsop l I Other l I Other Notified Commentt "
- Shift.supervise:, ,,,_ _ _
.1 inwt Reportable E I 36.465 lel~l)(ll .l 1 36.34 Icl(R) I I $6.?l (el(2)I(iv I I 30.73 (al(l)(viiil(5J"
- t1 PDS I I 3e.465 IapllI~iil l 1 56.71 (e1(21(11 ( I 56.13 le(a)(2I/vi) I I 5o.73 .JII3)taIs Fire Bogert I I 20.463 4(.11i111i) 1 1 56.73 (el(21(li? I 1 50.73 (M1l(l(vili) I I 3.71 (b)
IIS0. l 1 30.465 (e6li nV) I I 6.73 1l012111) I I 50.73 (eli(2)vill)(A) I I (ei
.1I Part 21 26.4l (.l(i1(vi 13.71 I I 26.662 fbI I 1 40.362 I Other -
3 l 36.465 l l 36.36 (a) le)ll) I -omneute /. ivaluation .
mm~wmummmmmmmmmmmmummnu mfmuinmfei~aaiNmwunaeu muuuumueuin ~ mmmlmmmwmml~mmmmmaubunmumn~u mumuuuummiN um inw~.inmumm u.m u.,.....im Agree / lilagaree with Est avalubtin - Additional Corrective Action Process Required:
Comments:
Comments
Alto* / Disagree with ins teoensendatiou Comeant. /'Other Acties Desired U evonmIs copectrbae, submit copy of R'o o r.' V., OpS.
P I ** / ....... . 'lsmc / ,/
Alp ee' a No .22 ,page I ot* I t DI #91-01
. 14-AUG-92 14:20:22
- VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE.DATE..........: 14-AUG-92 14: 05: 00' .
-D /
SAMPLE IDENTIFICATION:
TYPE OF SAMPLE .... .. :
TB 222 SPILL 23ML.SCINT. VIAL ", -w0ý SAMPLE QUANTITY ..... c 23.00000 UNITS: NL SAMPLE GEOMETRY.4.....: VY2004 ea. L OPERATOR OR EFFICIENCY FILE NAME.: EFF.VY2004,
- ACQUIRE DATE: 14-AUG-92 14:11:45 FWHM(1332) 1.867 PRESET TIME(LIVE): 500. SEC
- SENSITIVITY: 5.000 ELAPSED REAL TIME: 508. SEC
- SHAPE PARAMETER 10.0 %
ELAPSED LIVE TIME: 500. SEC NBR ITERATIONS:* 10.
- .3~I *********~*********************
DETECTOR..: 20% HPGE LIBRARY NUCL .LIBI CALIB DATE: 14-A UG-92 00:56:04 : ENERGY TOLERANCE 1.500KV KEV/CHNL..: 0.50)01629 .* HALF LIFE RATIO 8.00 OFFSET.... : -0.10 '59622 KEV ABUNDANCE LIMIT 80.00%
- 0. COEFF..: 0.00OE-01 KEV/C**2
- DECAY TIME*(MIN) 6.0 ENERGY WINDOW 24.90 TO '2048.56 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC.%ERR FIT 1 .0 80.30 1079. 3153. 1.52 160.75 155 12 2.16E 00 '10.9.
2 0 140.56 643. 2543. 0.94. 281.24 .277 9 1.29E 00 14.7
.3 0 145.55 671. 1928. 1.13 291.21 288 7 1.34E-00 .11.6 4 6 162.74 372. 1985. 1.13 325,59 322 15. 7.44E-01 20.5 1.49E OC 6 165.88 1891. 1654. 1.04 331.86 322 15 3.78E 00. 4.1 6 0 :220.46 432. 2262.' 1.15 440.98 437. 8 8.64E-01 19.5 7 0 249.77 4786. 2705. 1.12 499.59 494 11 9.57E.00 2.6 8 5 284.27 752. 1685. A1.13 568.58 562 20 1.50E 00 -.97 6. 33E-01 9 5 288.46 596. 1775. 1.12 576.94 562 20 .1.19E.00 12.2
.1.00 657.60 654 8-8.66E-01, 19.6
- 10 0 328.80 433. 2218.
0 364.49 .:8637. 2304.. 1.19 728.94 722 141.73E 01 1.6 12 0 417.86 563. 1040. 1.21 835.66 832 11 !ýl. 13E 00 12.2 13 0 *423.50 156. 855. 1.01 846.94 *842 9 3.11E-01 34.4 14 0 434.28 "204. 1498. 4.49 868.48 862 16 4.08E-01 144.-0 "933.' " 7.7 15 0 487.07 998. 1.27 974.03 968 13 1.87E 00 416 .0 511.00 28700. 2006. 2.62 1'21.88 1014 19*5.74E 01 10.7 17 2 522.60 %D9.9. 414. 1.29 1045.07 1042 24 7.98E-01. 9.2 1.78E 00 1i 2 526.62. 2i18. 599. 1.43 1053.11 1042 24 4.24E 00 3.1 19 2 529.92 13207.. 448. 1.31 1059.70 1042 24 2.64E 01 0.9 20 0 537.21 .537. 636. 1.25 1074.28 1069 11 1.07E 00 10.4 21 0 546.52 821. 464. 1.33 1092.90 1088 10.1.64E 00 6.2 22 0 555.57 1134. 546.. 1.30 1110.99 1105 12 2.27E'00 5.1 23 0 595.47 194. 416. 1.39 1190.76 1186 10 3.87E-01 21.7 C. (m[rp-) wLf,-
ENERGY WINDOW 24.90 TO 2048.56 1.00-SIGMA %ERR PK .I T ENERGY BKGND FWHM. CHANNEL LEFT PW CTS/SEC %ERR FIT 24 0 621.60 249. 579. 1.83 1243.01 1237 13 4.98E-01 21.8
'351. 595. 1.27 1260.38 1254 13 7.03E-01 15.7 25 0 630.29 *355.
26 0 637.08 428. 1.40 1273.95 1269 10 7.1OE-01 12.6 27 0 652.91 114. 344. 1.18 1305.61 1303 7 2.28E-01 29.8 28 0 667.67 2190. 792. .1.39 1335.12. 1327 16 4.38E 00 3.6 29 7 677.47 93. 272. A.1.21 1354.71 1351 13 1.85E-*01. 31.9 1.53E OC 30 7 679.90 76. 291. 1.21 1359.58 1351 13 1.51E-01 38.9 31 0 707.04 251 356. 1.75 1413.83 1409 11 5.03E-01 16.4 32 0 722.98 129. 330. 1.65 1445.71 1440 11 2.57E-01 28.6 33 0 728.08 101. 439. 4.73 .1455.90 1451 14 2.03E-01 45.6 34 0 749.99 469.. 437. 1.66 .1499.70 1494 15 9i38E-01 10.7 1371. 314. 1.59 1545.05 1540 11 2.74E*00 3.8 35 0 772.67 36 0 816.00 262. 378. 1.52 1631.68 1628 11 5.24E-01 15.9 37 0 836.91 502. 260. 1.64 1673.49 1669 11 1..OOE 00 *7.8 38 0 847.05 1290. 365. 1.62 1693. 77 1685 16 2.58E 00 4.4 39 0 856.82 203. 306. 1.69 1713.28 1707 13 4.06E-01 19.4 40 0 875.28 477. 286.. 1.60 1750.21 1745 12 9.54E-01 8.7.
41 .0 884.26 836. 306. 1.60 1768.15 1762 13 1.67E 00 5.8 42 .0 925.78 97. 322. 1.46 i851.17 1843: 13 1.95E-01 41.4 1.95 43 0 954.31 350. 271. 1908.21 1900 16 6.99E-01 12.1 44 0 973.39. 136. 363. 3.37- .1946.35.1940" 15'2.71E-01 3i.6 45 0 1024.33 3?3. 232. 1.71 2048'20 2043 12 7.86E-01 .*9.8 323. 1.85 2076.96 2068 15 1.1OE 00. 83 46 0 1038.7i 552.
47 0 1072.91 150. 178. 1.63 2145.33 2139 13 3.0OE-01 20.6
- 168. 17 3.35E-01 22.3 48 0 1101.64 189. .2.25 2202.78 2195
- 49. 0 i123.98 220. 229. 1."34 *2247.44 2240 15 4.40E-01 17.5
.50 2 1131.61 1273. 124. 1.75 .2262.70 2257 21 2.55E 00 3.4 1.81E OC 51 2 1136.11 165. 127. 2.09 2271.69 2257 21 3.31E-01 .19.5 52 0 1237.85 .200. 220. 5.48 2475.11 2463 22 4. 00E-01 21.5 1670. 128. 1.81 2520.50 2514 15 3..34E 00. 2.9 53 0 1260.56 54 0 1298.36 154. 165. 1.98 2596.09 2590 13 3.08E-01 19.6 55 0 1384.30 239. 91. 1.68 2767.91 2761 13 4.78E-01 10.5 56 0.1398.81 88. 69. 0.78. 2796.92 2793 10 1:76E-01 23.1 57 0 1457.50 440. 155. 2.05`2914.27 2906 19 8.80E-O1 8.4 58 0.1502.24 36.. 77. 1.56 3003.72 2996 14 7.28E-02 54.5 59 0 1566.36 42. 53.. 1..11 3131.90 3128 11 8.31E-02 36.6
.60 0 1596.33 552. 38. 1.97 3191.84 3184 17 1.10E GO 5.0 61 0"1678.22 436. 42. 1.75 3355.57 3349 14 8.71E-01 .5.9
.62 0 1706.72 1.73. 33. 1.52* 3412.54 3405 16z-'.46E-01 11.3 63 0 1791.32 369. 11. 1.97 3581.69 3574 15.7.38E-01 5.9 64 0.1808.01 46. 21. 2.23 3615.05 3606 18 9.16E-02 -31..5 65 0 1831.43 23. 5. 0.61. 3661.87 3659 9 4.61E-02 "33.1 PEAK SEARCH COMPLETED (REV 15.7)
NU.;L1lUE ILl-NIlI-IL;M1UN SY]iEMi (REV JUN 87)
SUMMARY
. OF NUCLIDE ACTIVITY PAGE 1' TOTAL. PEAKS IN SPECTRUM 65 UNIDENTIFIED PEAKS 31
.IDENTIFIED IN
SUMMARY
REPORT 34 52.31%
FISSION GAS 1.00-SIGMA 1.00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-131M FG. 11. 90D 1.S000 5.739E-4 1.176E -4 20.50 XE-133. .FG 5.25D 1.001 7.835E -5 8.579E -6 10.95.
XE-135 FG 9. 08H .1.014 2.349E -4 6.013E -6 2.56 XE-135M 'FG 15. 65M 1.617 3.579E -4 1.102E -5
- 3.08 FISSION PRODUCT 1.00-SIGMA 1-.00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI./UNIT ERROR %ERR TC-99M FP 6. 02H 1.021 1.995E -5 2.934E -6 14.71 1-131 FP 8.04D 1.001 6.398E -4 1.019E -5 1.59 I-132r FP 2.30H 1.057 2.487E -4 8.926E -6 3.59 1-133 FP 20. 80H 1.006 1.296E -3 1.191E -5 0.92 A-134 FP 52. 60M 1.155 2.216E -4 1.286E -5 '5.81 1-135 FP 6. 61H 1.019 1.220E -3 3.537E -5 2.90 SR-91 FP 9. 50H 1'.013 2.034E -4 1.991E -5 9.79 SR-92 FP 2.71H 1.048 6.18SE'-5 6.479E -6 10.47 Y-91M FP 49. 71M. 1.165 1.236E -4 6.291E -6 5.09 RU-106 FP 368. 20D 1.000 2.509E -4 5.458E -5 21.75 BA-139 FP 82.71M 1.096 3.536E -4 1.458E -5 4.12 BA-140 .FP 12. 79D 1.000 1.853E -4 1.934E -5 10.44 LA-140 FP 40.22H 1.003 1.473E -4 7.407E -6 5.03 CE-141 32. OOD 1.000 3.78SE -5 4.407E -6 11.64 1.
14-AUG-92 1.4:29:56 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DATE .......... : 14-AUG-92 14:10:00 I ýý-t,-f1 SAMPLE IDENTIFICATION: TB CLEAN SUMP TYPE OF SAMPLE ....... : LIQUID MARINELLI SAMPLE QUANTITY...... : 1000.000 UNITS: ML SAMPLE GEOMETRY* ..... : VY2005 OPERATOR .............. : SCM EFFICIENCY FILE NAME.: EFF.VY2005*,
ACQUIRE DATE: 14-AUG-92.14:24:21
- FWHM(1332) 1.867 PRESET TIME(LIVE): .2000. SEC
- SENSITIVITY: 5.000 ELAPSED REAL TIME: 326. SEC
- SHAPE PARAMETER.: 10.0 %
ELAPSED LIVE TIME: 326. SEC
- NBR ITERATIONS: 10.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIB1 CALIB DATE: 14-AUG-92 00:56:29 *.ENERGY TOLERANCE 1.500KV.
KEV/CHNL...: 0.5001629
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1059622 KEV
- ABUNDANCE.LIMIT 80.00%,
Q. COEFF;.: O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO .2048.56 1.00-SIGMA %ERR PK-IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT
.1 .0 249.61 39. 31. 1.71 499.26 497 6 1.21E-01 29.0 2 0 364.48 132. 30o. 1.21 728.93 724 10 4.05E-01 12.1 3 0 489.82 7. 71. 1,15 979.53 978 6 2.07E-02 89.5 8.-
4 0 511.06. 625. " 2.57 1022.00 1014 18 1.92E 09 4.3 5 0O 529.93 204. 13. 1.34 1059.73 1056 9 6.27E-01 8.2 6 0 667.92 39. 4. 2.34 1335.62 1327 16 1.19E-01 19.7 7 .0 772.51 27. 2. 1.32 1544.72 1538 12 8.37E-02 25.1 8 -0 846.74 19. 4. 1.00 1693.15 .1690 8 5.68E-02 30.1
.9 0 884.87 .13.. "0. 1.16. 1769.38.1764 12 3.99E-02 .27.7 10 0 1131.80 14. 16. 0.71 2263.07 2253 13 4.25E-02 56.7 11 O, 1260.39. 36. 0. 0.77 2520.17 2511 18*1.10E-01 20.8 PEAK SEARCH .COMPLETED (REV. 15.7)
N:.2'LIDE IDENTIFICATION SYSTEM (REV JUN 87)
SL:IMMRY OF NUCLIDE ACTIVITY PAGE 1 fOTAL PEAKS IN SPECTRUM 11 UNIDENTIFIED PEAKS 4 1DENTIFIED IN
SUMMARY
REPORT. 7 63.64%
FISSION GAS 1.00-SIGMA 1.00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR 1.022 1.914E -7 5. 553E -
XE-135 FG .9.'08H 29.01 FISSION PRODUCT 1.00-SIGMA 1.00-SIGMA NUCL IDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR 1-131 FP 8.04D 1.001 8.944E -7 1.084E -7 12.12.
1-133 FP 20.80H 1.010 1.761E -6 .1.436E -7 8.15 1-134 FP 52. 60M 1.252 *R3.045E -7 8.445E -8 27.73 1-135 FP 6.61k1 1.030 2.127E -6 4.432E -7 20.83
- 1.
4
S**:, -x**~ ******* 14-AUG-92 15:01: 15 VERMONT YANKEE NUCLEAR POWER CORPORATION _
SAMPLE DATE .......... 14-AUG-92 14:10:00 " \
TB CLEAN SUMP SAMPLE IDENTIFICATION:
TYPE OF SAMPLE. ..... : LIQUID MARINELLI coL*
- SAMPLE QUANTITY ...... : i000.000 UNITS: ML SAMPLE GEOMETRY ...... : VY2005 OPERATOR ............. : sCMq EFFICIENCY FILE NAME.: EFF.VY2005 7, ACQUIRE DATE: 14-AUG-92 14:24:21
- FWHM(1332) 1.867 PRESET TIME(LIVE): 2000. SEC
- SENSITIVITY: 5.000 ELAPSED REAL TIME: 2001. SEC
- SHAPE PARAMETER i0.0 %
ELAPSED LIVE TIME: 2000. SEC
- NBR ITERATIONS: i0.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIB1 CALIB DATE: 14-AUO-92 00:56:29
- ENERGY TOLERANCE 1.500KV KEV/CHNL..: 0.5001629
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..: O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO 2048.56 I.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHN CHANNEL LEFT PW CTS/SEC %ERR FIT i 249.91 264. 425. 1.21 499.87 494 12 1.32E-01 17.3 284.07 71. 228. 1.45 568.17 565 8 3.56E-02 40.7 d2."
364.45 167. 1.26 728.88 724 9 4.13E-01 4.6 4
417.86 86. i25. 1.11 835.67 829 12 4,28E-02 30.0 511.04 3455. 168. 2.53 1021.96 1014 22 1.73E 00 2.0 6 526.51 158. 54. 1.53 1052.88 1049 17 7.88E-02 10.8 1. 36E O(
7 529.91 1239. 45. 1 33 1059.68 1049 17 6.19E-01 3.0 8 546.81 84. 43. 1.49 1093.49 1089 4.20E-02 20.2
- 38. 1274.62 1268 10 1.86E-02 38.0 637.41 37. 1.27 10 667.81 240. 37. 1.53 1335.40 1329 15 1.20E-01 9.0 i 1 772.69 146. 16. 1.75 1545.09 1538 13 7.28E-02 11.5 12 836.86 53. 2.11 1673.38 1668 11 2.65E-02 24.3 13 847.23 61. 52.
- 18. 1.13 1694.12 1687 14 3. 03E-02 .27.2 14 875.46 58. 18. i. 32 1750.57 1743 15 2.90E-02 %20.8 15 884.18 62. 19. 1. 01 1768.00 1763 11 3.08E-02 120.8 16 953.9? 30. 18. 1.74 1907.56 1902 11 1.50E-02 40.4 17 1038.59 76. 26. 1 .87 2076.71 2069 17 3.80E-02 20.6.
18 1131.46 132. 9. 1.70 2262.40 2258 10 6 .58E-02 10.1 19 126 0.30 195. 4. 1.51 2519.99 2511 18 9.73E-02 8.0 1298.49 13. 9. 1.42 2596.36 2592 10 6.52E-03 52.6 21 1457.57 80. 0. 2.44 2914.40 2905 22 4.OOE-02 13.1 22 1677.60 50. 0. 1.86 3354.32 3348 15 2.50E-02 14.1 23 1790.53 42. 4. 1.75 3580.10 3573 13 2.11E-02 19.4 PEAK* SEARCH COMPLETED (REV 15.7) 4
NUCLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUNM.1ARY'OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM UNIDENTIFIED PEAKS 1DENTIFIED IN
SUMMARY
REPORT 14 60O.87%
FISSION GAS 1.00-SIGMA 1,00-SIGMA NUCLIDE SDHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-135 FC 9.08H 1.040 2. 131E -7 3.690E -8 17.32 XE-1335M FG 15.65M 3.614 8.495E -7 9.141E -8 10.76 FISSION PRODUCT 1.00-SIGMA 1. 00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR
- 9. 131E -7 4.185E -8 4.58 1-131 FP 8.04D 1.002 1-132 FP 2.30H 1.167 4.189E -7 3.750E -8 8.95 1-133 FP 20.80H 1.017 1.753E. -6 5.285E -8 3.02 1-134 FP 52.60M 1.493 2.799E -7. 5.830E -8 20.83 1-135 FP 6.61H 1.056 1.920E -6 1.527E -7 7.96 4
1s IoI
-1 I.. b -o'
. 1 00 lot 101 t 2 13 IC 111o 1 101
-1P10 I.
Vt CPS LOG Ii 9 1111i 0cr 10 01o ' 12 o3 1o4 1101 to.
- cbps Aoc f.
- I I II I JbI *I'*ti. ILb
A~********4A-**** 4~******
- 14-AUG-9214020:56 ******
VERMONT YANKEE I NUCLEAR POWER CORPORATION SAMPLE DATE ..... : 14-AUG-92 14:10:00 SAMPLE IDENTIFICATION: .TB CLEAN SUMP glo 31~a(Q TYPE OF SAMPLE ....... : LIQUID MARINELLI SAMPLE QUANTITY ...... : 1000.000 UNITS: ML SAMPLE GEOMETRY,.... VY2005 OPERATOR ............. : SCM EFFICIENCY FILE NAME.: EFF. VY2005,,
ACQUIRE DATEY 14-AUG-92 14:24:21
- FWHM(1332) 1.867 PRESET TIME(AIVE): 2000. SEC
- SENSITIVITY: 5.000 ELAPSED REAL :T IME: 326. SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME: 326.,SEC
- NBR ITERATIONS: 10.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIB!
CALIB DATE: 14-AUG-92 00:56:29
- ENERGY TOLERANCE 1.500KV KEV/CHNL..: 0.5001629
- HALF LIFE RATIO .040 OFFSET....: -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
- 0. COEFF..: O.O00E-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO 2048.56 -
1.00-SIGMA %ERR PK IT ENERGY AREA DKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT 1 0 249.61 39. Si.
- 30. 1.71 499.26 497 6 1. 21E-01 29.0 2 0 364.4S 132. 728.93 724 10 4. 05E-0 1 12.1 2 0 489.S2 7. 7. 1.,15 979.53 978 6 2. 07E-02 89.5 4 0 511.06 625, 1. 2.57 1022.00 1014 18 1.92E 00 4. 3 5 0 529.93 204. 13. 1 .34 1059.73 1056 9 6.27E-01 8.2 6 0 667.92 37. 4. 2.34 1335.62 1327 16 1. 19E-01 19.7 7 0 772.51 27. 2. 1.32 1544.72 1538 12 8. 37E-02 25.1 8 0 846.74 19. 4. 1.00 1693.15 1690 8 5. 68E-02 30. 1
? 0 354.87 13. 0. 1.16 1769.38 1764 12 3. 99E-02 27.7 10 0 1131.80 14. 16. 0.71 2263.07 2253 13 4.25E-0r2 56.7 11 0 1260.39 36. 0. 0.77 2520.17 2511 18 1. OE-Ol 20.8 PEAK SEARCH COMPLETED (REV 15.7)
NUCLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM 11 UNIDENTIFIPD PEAKS 4 IDENTIFIED IN
SUMMARY
REPORT 7 63.64%
FISSION GAS 1.00-SIGMA I.O0-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-135 FO 9.08H 1.022 1.914E -7 5.553E -8 29.01 FISSION PRODUCT 1.00-SIGMA 1.00-SIGMA NUCLIDE SEBHR HLIFE DECAY UCI /UNIT ERROR %ERR 1-131 FP 8. 04D 1.001 8.944E -7 1.084E -7 12.12 1-133 20. SOH 1.010 1.761E -6 1.436E -7 8.15 1-134 FP 52. 60M 1.252 3.045E -7 8.445E -8 27.73 1-135 FP 6.61H 1.030 2.127E -6 4.432E -7 20.83
3
+/-4-AUG-92 14:20:224 VERMONT YANKEE NUCLEAR POWER CORPORATION r
41Ioo, SAMPLE DATE ........... : 14-AUG-92 14:05:00 SAMPLE IDENTIFICATION: TB 222 SPILL J-,
TYPE OF SAMPLE ....... : 23ML SCINT. VIAL SAMPLE QUANTITY ... . 23.00000 UNITS: ML ek 6v SAMPLE GEOMETRY ...... : VY2004 OPERATOR .............. : OR EFFICIENCY FILE NAME.: EFF.VY2004,7 ACQUIRE DATE; 14-AUG-92 14:11:45
- FWHM( 1332) 1.867 PRESET TIME(IbVE): 500. SEC
- SENSITIVITY: 5.000 ELAPSED REAL iIME: 508. SEC
- SHAPE PARAMETER : 10.0 0 ELAPSED LIVE tIME: 500. SEC
- NBR ITERATIONS: 10.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIB1 CALlIB DATE: 14-AUG-92 00:56:04
- ENERGY TOLERANCE 1Q500KV KEV/CHNL.: 0.5001629
- HALF LIFE RATIO 8.00 OFFSET....: -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..: O.O00E-01 KEV/C**2
- DECAY TIME (MIN) 6.0 ENERGY WINDOW 244.90 TO 2048.56 ,
1.00-SIGMA %ERR PK IT ENERGY AREA BKGND " FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT A 0 80.30 1079. 3 153. 1.52 160.75 155 12 2. 16E 00 10.9 0 140.56 6143. 2543. 0.94 26 1. 24 277 9 1.29E 00 14.7 2
0 145.55 671. 1928. 1.13 291.21 7 1.34E 00 11.6 4 6 162.74 .372. 1985. +/-1.13 32'5. 59 L15 7. 44E-01 20.5 1.4S'E n-00 5 6 165.88 1891. 1654. 1.04 331.86 322 -5 3.78E 00 4.1 6 0 220.46 432. 2262. 1.15 440.98 437 8 8.64E-01 1 .5 7 0 249.77 4786. 2705. 1.12 499.59 494 11 9.57E 00 2.6 C 5 284.27 752. 1685. 1.18 568.58 562 20 1.50E 00 9.7 6.33E-01 7 5 288.46 596. 1775. 1.12 576.94 20 1.19E 00 12.2 10 0 328'. 80 4 3. 2218. 1.00 657.60 654 C 8. 66E-01 19.6
- 1. i9 1i 0 364.49 8637. 2304. 1.19 728.94 722 14 1.73E 01 1.6 12 0 417.86 563. 1040. 835.66 632 11 1.13E 00 12.2 13 0 423.50 156. 855. 1.01 846.94 842 3. 1 IE-O0 34.4 14 0 4344.28 204a 1498. 4.49 868.48 662 16 4.O8E-01 44.0
+/-5 0 487.07 933. 998. 1.27 974.03 968 13 1.67E 00 7.7 16 0 511.00 28700. 2006. 2.62 1021.88 1014 19 5.74E 01 0.7 17 0 522.60 399. 414. 1.29 1045.07 1042 24 7. 98E-01 9.2 1. 76E 00 2
526.62 2118. 599. 1.43 1053. 11 1042 24 4.24E 00 3.1 2 1. 3 19 529.92 13207. 448. 1059.70 1042 24 2.64E 01 0.9 20 0 537.21 537. 636. 1.25 1074.28 1069 11 1.07E 00 10.4 0 1.31 21 0 546.52 821. 464. 1092.90 1088 10 1.64E 00 6.2 S55.57 1134. 546. 1.30 1110.99 1105 12 2.27E 00 5.1 2? 595. 47 194. 416. 1.39 1190.76 1186 i0 3. 87E-01 -21.7
ENERGY WINDOW 24.90 TO 2048.56 lO0-SIGMIA %ERR PK I T ENERGY AREA BKGND FWHM CHAiNEL LEFT FW CTS/SEC %ERR FIT 24 621.60 249. 579. 1. 83 1243.01 1237 13 4.98E-01 21.8 630.29 35 1. 595. 1.27 1260.38 1254 13 7.03E-01 15.7 45 637.08 S-55. 428. 1.40 1273.95 1269 10 7. 10E-01 12.6 2Co%
27 652.91 114. 344. 1.18 1305.61 1303 7 2.28E-01 29.8 16 4.38E 00 3.6 340 667.67 2190. 792. 1.39 1335. 12+/- 1327 272. 1.21 1354.71 1351 13 1.0-5E-01 31.9 1. 53E 00 677.47
- 76. 291. 1.21 135-9. 58 1351 13 1.51E-01 38.9 679.90 31 707.04 25. . 356. 1.75 1413.83 1409 11 5.03E-01 16.4 32 722.98 129. 330. 1.65 1445.71 1440 11 2.57E-01 28.6 33 728.08 101. 439. 4.73 1455.90 1451 14 2.03E-01 45.6 34 749. ý9 469. 437. 1. 6L'. 1499.70 1494 15 9.38E-01 10.7 3.5 772.67 1371. 314. 1.59 1545.05 1540 11 2.74E 00 Zn 6-36 816. 00 262. 378. 1. 52 1631.68 1628 11 5.24E-01 15.9 37 83,.91 502. 260. 1.64 1673.49 1669 11 1.OOE 00 7.8 38 847. 05 1290. 365. 1.62 1693.77 1685 16 2.58E 00 4.4 39 856.82 203. 306. 1.69 1713.28 1707 13 4.06E-01 19.4 40 875.2-8 477. 286. 1.60 1750.21 1745 12 9.54E-01 8.7 884.26 1i. 60 1768.15 1762 13 1.67E V0 5.8 41 836. 306.
42 925.78 97. 3.-4-4 1.46 1851.17 1843 13 1.95E-01 41.4 43 954.31 350. 271. 1.95 1908.21 1900 16 6.99E-01 12. 1 44 973.39 136. 363. 3.37 1946.35 1940 *15 2.71E-01 31.6 45 1024.33
.Lý .C.
2 3 2 . 1.71 2048.20 2043 12 7.86E-01 7.8 1.85 2076.96 2068 15 1.1OE 00 S.,3 46 1038.71 55-.4.
47 1072.91 150. 178. 1.63 2145.33 2i39 13 3.00E-01 20.6 48 1101.64 168. 189. 2.25 2202. 7/8 2195 17 3.35E-01 22.3
- i -Z3.98 229. 1.34 2247.44 2240 15 4.40E-01 17.5 49 1131.61 50 1273. 124. 1.75 2262.70 2257 21 2.55E 00 3.4
-51 165. 127. 2.09 2271.69 2257 2'1 3.31E-01 i?. 5 1136.11 1-237.85 5.48 2475.11 2463 -2 4.OOE-01 21 .5
,52 1260.56 200. 220.
53 1670. 1.81 2520.50 2514 15 3.34E 00 19.6 54 1298.36 154. 165. 1.98 2596.09 2590 13 3.08E-01
ý55 239. 91. i. 68 2767.91 2761 13 4.78E-01 56 1384. so
- 88. 69. 0.78 2796.92 2793 10 1.76E-01 23. 1 1398.81 8.4 155. 2. 0-5, 2914.27 2906 19 8.80E-01 57 1457.50 440. 54.5 1502.24 77. 1.56 3003.72 2996 14 7.28E-02
~5.9 53. d13.d90 136.6 1566.36 42. 1.11 3128 11 8.31E-02 5.0 60C 1596. 33 552. 38. 1 97 3191.84 3184 17 1.1OE 00 5.9 61 1678.22 436. 175 3355.57 3349 14 8.71E-01 173. 33. 1.52 3412.54 3405 16 3.46E-01 11,3 62 1706.72 5.9 369. ii. 1.97 3531.69 3574 15 7.33E-01 63 1791.32 64 1808.*01 46. 21. 2.23 3615.05 3606 18 9.16E-02 31.5
- 5. 33.-1 65 1831.43 23. 0.61 3661.87 3659 9 4.61E-02 PEAK SEARCH COMPLETED (REV 15.7)
SULMgARY OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM 65 UNIDENTIFIED PEAKS 31 IDENTIFIER IN
SUMMARY
REPORT 34 52.31%
FISSION GAS 'C.-
1.00-SIGMA 1 . 00-SIGMA NUCL IDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-J 31N FG 11. 90D 1.000 5.739E -4 1.176E -4 20.50 7.835E -5 S. 57E -6 10.95 XE-133 FG 5. 25D 1.001 XE-135 9. 08H 1.014 2.349E -4 6.013E -6 2.r.56 FG 15. 65M 1 .617 3.579E -4 1.102E -5 3.08 XE-135M FISSION PRODUCT 1.00-SIGMA 1.00-SIGMA NUCL IDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR TC-99M FP 6. 02H 1.021 1.995E -5 2.934E -6 14.71 1-131 FP S.04D 1.001 6.398E -4 1.019E -5 1.59 1-132 FP 2.30H 1.057 2.487E -4 8.926E -6 3.59 1-133 FP 20. 80H 1. 006 1.296E -3 1.191E -5 0.92 1134 FP 52. 60M 1.155 2.216E -4 1.286E -5 5.81 1-135 I. - L 3D 5 FP 6.61 H 1.019 1.220E -3 3.537E -5 2.90 SR-91 FP 9 *50H 1.013 2.034E -4 1.991E -5 9.79 SR-92 nr 71H 1.048 6. 188E -5 6.479E -6 i0.47 FP Y-91M1 49. 71M 1.165 1.236E -4 6.291E -6 5.09 RU-i06 FP 368.20D 1.000 2.509E -4 5.458E -5 21.75 BA--139 FP 82.71M 1.096 3.536E -4 1.458E -5 4.12 BA-140 FP 12. 79D 1.000 1. 853E -4 1.934E -5 10.44 LA_-140 FP 40.22H 1. 003 1.473E -4 7.407E -6 5. 03 CE-141 FP 32.00D 1. 000 3.788E -5 4.407E -6 11.64
17-AUG-72 14:43:10 VERMONT YPNKEE NUCLEAR POWER CORPORATION SAMPLE DATE.; ........ : 17-AUG-92*i.:0:00 SAMPLE IDENTIFICATION: TB SUMPfLD TYPE OF SAMPLE ....... : LIQUID MA'INELLI SAMPLE QUANTITY ...... : i000.000 UNITS: ML SAMPLE GEOMETRY ...... ; VY2005 OPERATOR ............... : SCM EFFICIENCY FILE NAME.: EFF.VY2005 7 7 ACQUIRE DATEJ 17-AUG-92 14 09:38
- FWHM(1332) 1.845 PRESET TIME(LIVE): 2000. SEC
- SENSITIVITY: 5.000 ELAPSED REALOJIME: 2002. SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME: 2000. SEC
- NBR ITERATIONS: 10.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIBl CALIB DATE: 17-AUG-92 00:27:05
- ENERGY TOLERANCE 1.500KV KEV/CHNL..: 0.5001556
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1080463 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..: O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 9.0 ENERGY WINDOW 24.90 TO 2048.53 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT 1 0 80.69 2549. 1459. 1 . 44 161.55 156 10 1.27E 00 3.5 150. 1617. 2.32 282.48 276 11 7.50E-02 53.1 0 141. 18 291.03 288 7 4.56E-01 6.8 0 145.45 912. 1028. 1.09 1.11 325.08 321 9 2.38E-01 16.0 4 0 162.48 475. 1522.
5 0 249.92 169. 577. 1.11 499.91 496 8 8. 43E-02 26.0 6 0 284.39 1336. 545. 1.15 568.82 564 11 6.68E-01 4.5 7 304.71 149. 430. i. 19 609.44 606 8 7.43E-02 26.3 0 328.80 894. 382. 1.10 657.60 654 8 4.47E-01 5.2 10 0 364.49 14625. 396. 1.22 728.96 723 13 7.31E 00 0.9 10 0 423.81 120. 127. 1.18 847.58 844 9 5.99E-02 20.2 0 432.38 91. 162. 0.76 864.70 859 11 4.53E-02 30.9 12 0 438.21 56. 150, 0.97 876.37 872 10 2.79E-02 44.6 i3 0 487.03 1438. 113. 1.34 973.97 968 14 7.19E-01 3.1 14 0 510.50 79. 73. 1.79 1020.90 1017 9 3.97E-02 26.7 15 13 1.16E 00 2.3 0 529.91 2326. 137. 1.30 1059.72 1053 16 0 537.27 700. 98. 1.41 1074.41 1067 15 3.50E-01 4.9 17 0 636.96 836. 54. 1.43 1273.74 1266 13 4.18E-01 4.0 0 722.91 185. 46. 1.21 1445.59 1442 10 9.27E-02 10.9 19 0 751. 52 113. 35. 1.32 1502.79 1497 11 5.65E-02 161.
20 0 815.79 568. 41. 1.79 1631.29 1624 15 2.84E-01 5.0 21 0 857.56 26. 57. 3.58 1714.81 1709 19 1.30E-02 81.0 22 0 867.86 137. 21. 1.28 1735.39 1730 12 6.87E-02 12.9
.23 14 4.55E-02 15.9 875.13 91. 21. 1.52 1749.93'1742
ENERGY WINDOW 24.90 TO 2048.53 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT 919.38 22. 1.38 1838.41 1831 13 3.13E-02 21.4 24 0 63.
25 0 925.31 1 80. 16. 1.47 1850.26 1844 14 8.99E-02 9.3 26 0 1596.12 04. 15. 2.18 3191.47 3183 19 5.52E-01 3.1 P'EAK SEARCH COMPLETED (REV 15.7)
NUCLIDE IDENTIFICATION SYSTEM (REV JUN. 87)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM 26 UNIDENTIFIFD PEAKS 8 IDENTIFIED IN
SUMMARY
REPORT 18 69.23%
FISSION GAS
- i. 00-SIGMA I.00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR XE-131M FG 11. 90D 1.001 1.151E -5 1.839E -6 15.98 XE-1S3 FG 5.20D 1.002 3.511E -6 1.217E -7 3.47 XE-135 FG 9. 08H 1.034 1.352E -7 3.519E -8 26.03 ACTIVATION PRODUCT.
1.00-SIGMA 1.00-SIGMA NUCLIDE SBHR HL.IFE DECAY UCI /UNIT ERROR %ERR ZN-69M AP H ,.80H 1.022 6.205E -8 2.765E -8 44.56 FISSION PRODUCT 1.00-SIGMA 1.00-SIGMA NUCLIDE SBHR HLIFE DECAY UCI /UNIT ERROR %ERR TC-99M FP 6. 02H 1.052 8 07E-e 4.249E -8 53.06 1-131 FP S. 04D 1.002 1.616E -5 1.423E -7 0.88 1-133 FP 20. 80H 1.015 3. 282E -6 7.609E -8 2.32 BA-140 FP 12. 79D 1.001 3.445E -6 1.678E -7' 4.87 LA-140 FP 40. 22H 1. 008 3.826E -6 1.182E -7 3.09 CE-141 FP 32. GOD 1.000 8.469E -7 5.718E -8 6.75 VERMONT YANKEE QUANTITATIVE RADIOISOTOPIC LLD ANALYSIS 17 AUG 1992 14:46:48 LIQUID SAMPLE
- NEXT TO LLD LIMIT INDICATES LLD NOT MET NUCLIDE LLD LLD LIMIT UCI/ML UCI/ML XE-133 3.745E-07 1. OE-05
- ISOTOPE POSITIVELY IDENTIFIED ****
XE-133M 7.360E-07 1.OE-05 XE-135 9.533E-08 1.OE-05
- ISOTOPE POSITIVELY IDENTIFIED ****
XE-138 3.637E-07 1.OE-05 KR-87 1. 173E-07 1.OE-05
MO-?? 3.9?22-E-07 5. OE" 07 FE-59 1. 143E--07 5. OE-07 CO-58 '5.024E-08 5. OE-07 CO-60 1-013E-07 5. OE-07 ZN-65 1. 431E-07 5. OE-07 I1-131 6. 245E-07 1. OE-06
- ISOTOPE POSITIVELY IDENTIFIED
- ISOTOPE POSITIVELY IDENTIFIED
- CE-144 6. 142E-07 5. OE-07
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Attachment, VYNPC, 8/20/92 D '~ P' K Overflow of Condensate Demineralizer Backwash Receiving Tank On August 14, 1992 at approximately 1330, while backwashing the B condensate demineralizer and transferring the contents to the condensate demineralizer backwash tank, the electric pump which transfers the water from the tank to radwaste failed, reyilt>. in the backwash receiving tank overflowing onto the floor. The water was radioactively contaminated and contained some resin material -e floor in the vicinity of the tank was flo,'Y-.d to a depth of approximately 1-2 inches.
Samples taken in ý ::earby sump indicated the presence of ..,z.ioctive Iodine and Tritium.
The sump purrqps are designed to cycle if required by level so it is possible that some contaminated water was discharged to the river by way of the service water system (10,000 gpm) and'then into the main circulating water system (360,000 gpm) before entering the Connecticut River.
The precise volume of contaminated water that may have been discharged to the river is estimated to be less than 15 gallons. Radiation monitors and samples at :irt (if discharge did r,"record any evidence of radioactivity and remained normal durn. .*
-e personnel isolated the sump pumps and terminated the poti-.ntial 6, ,..arge at
- v 1430.
,ical analysis of samples taken from the floor, sumps, and the discharge suming bounding conditions, Vermont Yankee calculated that Technical
-..i NRC 10CFR requirements and limits were not exceeded and the event was t re: the NRC. The calculated parameter values were also below : .-mont Aealth Radiological Health limits and the NPDES Permit limits.
"T' .. .ed values were based on the extremely conservative assumption.that rat.
wate. o pumped out of the sumps and discharged through the normal flow path"to th%.; ... r continuously during the event. The calculation assumes dilution by the flow of the Circulating Water system (360,000 gpm) occurring concurrently with the discharge.
The actual volume of radioactive water discharged is estimated to be three orders *.. magnitude below the bounding calculated values, or less than 15 gallons. Connecticut Rive: flowat the time of the incident was approximately 6000 cf-DJM.8/20/92 TrnT0l P S71
SUIiMARY OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases - The "Calculated Value is based upon the assumption that".
12000 gallons of radioactive water was pumped out -of the. TB Clean*
Sump and discharged, through the normal flow path, .to the river.
The calculation assumes dilution by the .. flow .of. 'Circulating Water(360000 gpm) occurring concurrently with this disicharge..:...,.*
APPLICABLE LIMITS * " E IIC'I" " : ' ::* : " :" -RELEASE
.LIQUID alculaite alue "
TECHINICAL SPECIFICATIONS
.jiquid.Effluents: Concentrations 1)T.S.3.8.A.1 - S 1 MPC as determined" .
by 10CFR20, App.B, Table II, Col. 2
" conc. (Noble Gases excluded) . " . 2.92E-*3 MPCs's 2)T.S.3.8.A.1 -'Total Noble.Gases Conc. e 2E-4 uci/cc 1.16E-9 uci/cc Liquid Effluents: Dose 1)Total Body .Dose -T.S.3.8.B.1 .
1.5 mrem in any quarter,-
3 mrem total for year 1.52E-6 mrem 2)Organ Dose -. T.S.3.8.B.I -
5 mrem in any quarter, I... El rn ... 4-.4.- 1L.L 4- , -.-W LL 1=4*u U %J G.L U.IW.L_yC z . . 7.47E-4 mrem' 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.92E-3 MPC's' NPDES REPORTING REQUIREMENTS Unplanned. Releases Yes 10CFR20 App
.(1 MPC) As 1B, Table II, Coi.2.
' .*.. 'M : *. '.2- 14PC's 2.92E-3 MPC.
Total*Radionuclides(excluding tritium)..:'..'.....
shall be _ 5 curies per year .. . -. 4.42E-4 curies Total Tritium shall be < 5 curies per year. 4.82E-4 'curies"..
Dose Calendar quarter - < 1.5 mren total*'body ';52E-6' mrex
- 5 5 mr.m to'any organ 7.47E-4* mrem`"?* :"..
Calendar year < 3 mrem total body. " .52E-6 mrem."
-" - < 10 mrem to any organ*,. .7.,47E;-4 mrem.
- pH - 6.5 to 8.5 Standard Units *w.:- : :7.6 Flow 14.4 million gallons per day *12000 gallon.
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
Additional action levels4
>2% of IE-7(or 2E-9)uci/ml*... 4. IOE-9 uci/ml Requires investigation, programs to reduce- releases and report to Vt.. Board of Health within 14 days (see regulation for additional details)
>4% of 1E-7(or 4E-9)uci/m14 4.10E-9 uci/ml Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup. report to Vt. Board of.
Health(see regulation for additional details)'
~limits) (see regulation for additional quarterly 30 Dissolved noble gases -I 4E-5 uci'/ml 1.16E-9 uci/ml (see regulation for additional quarterly limits) v-A
-.. 6j4,wj4~~~~~ ~eY-
ýee-eo .... "
IF:. ALARM RESPONSE SHEET PROCESS RADIATION MONITORING 3-F-6
- I Page 1 of 1
- I
- 1 SERVICE WATER Rev. 3 FFLUENT RAD HI uses: Setpoints: Actuating Devices:
- .-High background radiation 5.1 cps 1. RM-17-351
'lAevels. I'
References:
ii CWD 983 ON 3153 Conf irmation:
- 1. Service water rad monitor reading on RR-17-353 on CRP 9-2.
. Service water rad monitor RM-17-351 on CRP 9-10.
Automatiqc. Actions:
None rator Actions:
- 1. Verify radiation level is high in the service watersystem.
- 2. Check service-water and rad. monitor lineup.
- 3. Check for high background area radiation near service water i**1 4, rad. monitor.
- 4. Refer to ON 3153.
- I I.
- I
- 1t I.
f MEMORANDUM To: Van Bowman . Vernon Augustl20, 1992
.rrom: stv skb.os ernonLU.. ..
Subject:
Analysis of Station Air Compressor Blowdowh to* d6termine Appropriate Flow Pathway . .. ... .
Attachment:
- Memo from Steve McAvoy to Steve Skibniowsky,
. dated August*20, 1992, "TB Clean.Sump"
- " AS a*f0low up to our discussion concerning the appropriate fl67 pathway *for blowdown of condensed water from the Station Air S. Compressor, I have evaluated the attached memo from Steve McAvoy
.'concerning the analysis of some of the input sources to the TB
- Clean..Sump. I have 'concluded -that, given the .. radion'iilides identified in the compressor blowdown sample, the only appropriate method for disposal of this water is to send it.to Radwaste. The.
concentration of tritium and other nuclides 'exceeds, in this sample, the lower limit - of . detection for. tritium, and the "statistically significant" levels of the other huclides.
If you `:have questions concerning this Iconclusion, please contact me at.your earliest convenience.
. .4 .
.3;
MEMORANDUM To : Steve Skibniowsky Date: Augst 20, 1992 From : Steve McAvoy -Y-N File: 17.2
Subject:
TB Clean Sump Following the contamination *incident of the*Turbine Building Clean Sump at the 222' level on August 14,'1992, sources of water feeding that sump were checked to Environmental Release limiits for gamma emitters and tritium. The- following statistically significant radionuclides-were quantified:
Source Nuclide "Activity (uCi/ml)
Service Water Gamma, H-3 <Env. LLD Circ.* Water Gamma, H-3 <Env. LLD Station Air: H-3 5.7 E-5*
Compressor 1-133 1.05 E-88 Blowdown Cs-138 7.53 E-7 Ba-139 5.37 E-7 Y-91m 5.22 E-8 Xe-135 7.89 E-9 Although the dilution factors are. great and would probably result in the'total activity in the sump being below allowable' release limits, the discharge of the Air Compressor Blowdown to the TB *Clean Sump should be discontinued as it would constitute a release of radioactive liquid from the RCA.
19-AUG-92 20:08:15 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DATE .......... : 19-AU :00:00 SAMPLE IDENTIFICATION:
TYPE OF SAMPLE ....... : LIQUID MARINELLI SAMPLE QUANTITY ...... : 1000.000 UNITS: ML.
SAMPLE-GEOMETRY ........ : VY2005 OPERATOR ............... KLH EFFICIENCY FILE NAME.: EFF.VY2005,,
ACQUIRE DATEj 19-AUG-92 14:34:41
- FWHM(1332) 1.897 PRESET TIME(LIVE): 20000. SEC
- SENSITIVITY: 5.000 ELAPSED REAL *TIME: 20000. SEC
- SHAPE PARAMETER': 10.0 %
ELAPSED LIVE TIME: 20000. SEC
- NBR ITERATIONS: 10.
DETECTOR..: 20% HPGE
- LIBRARY NUCL .LIBI CALIB :DATE: 19-AUO-92 00:39:05
- ENERGY TOLERANCE 1.500KV KEV/CHNL..: .0.5001647 *-HALF LIFE RATIO 8.00 OFFSET....: -0.1161263 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..: O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 34.0 ENERGY WINDOW 24.89 TO 2048.56 1.00-SIGMA %ERR PK IT ENERGY. AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT
- 1 0 46.39 155. 286. 1.01 92.98 *89 .10 7.76E-03 22.3 24 0 62.81 111. 259. 1.09 125.82 121 9 5.54E-03 28.7 0 93.24 249. 374. 1.32 186.66 181 14 1.24E-02 17.9 34 506. 332.07 328 10 2.53E-02 7.4 0 165.97 242. 0.96 5 0 185.70 92. 145. 1.34 371.52 368 8 4.59E-03 26.0 6 0 238.42 33. 154. 0.86 476.91 474 8 1.65E-03 66.4 7 0 249.84 79. 106. 1.30 499.74 495 9 3.97E-03 27.6 8 0 462.79 141. 52. 1.33 925.51 922 9 7.04E-03 13.1 0 *510.80 205. 104. 2.19 1021.49 1014 16 1.03E-02 .13.3 10 0 529.46 67. 40. 4.34 1058.81 1052 14/3.37E-03 27.8 11 0 .546.45 40. 48. 0.68 1092.76 1087 12 1.99E-03 41.1 12 0 '555.30 52. 54. 0.92 1110.47 1108 9 2.58E-03 30.8 13 0 583.24 24. 34. 1.29 1166.32 1163 7 1.20E-03 47.1 0 871.41 30. 28. 0.76 1742.47 1736 10 1.51E-03 39.8 14 15 0 1009.08 85. 37. 1.77 2017.72 2009 14 4.27E-03 16.4 16 0 1435.37 127. 23. 1.49 2870.02 2865 13 6.33E-03 13.4
.17 0 1460.02 23. 9. 1.82 2919.32 2916 7 1.16E-03 33.3 PEAK SEARCH COMPLETED (REV 15.7) 0
- N3CLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1 TOTAL PEAKS IN SPECTRUM 17 UNIDENTIFLED PEAKS 8 IDENTIFIED IN
SUMMARY
REPORT 9 52.94%
FISSION GAS 1.00-SIGMA 1.00-SIGMA NUCLIDE SBHR C. CI /UNIT ERROR %ERR
.175E -9 27.57 FISSION PRODUCT 1.00-SIGMA 1'00-SIGMA NUCLIDE SBHR HLIFE DECAY ERROR %ERR qzq-? ' FP. 20. 80H 1.117 UC /UNIT. 2.912E -9 27.80 FP '49.71M 7.612 1.608E -8 30.79 FP 32.20M 15.150 1.009E. -7 13.39 FP 82.71M 3.979 3.973E -8 7.40 VERMONT YANKEE QUANTITATIVE RADIOISOTOPIC LLD ANALYSIS ,
19 AUG 1992 20:11:36
- NEXT TO LLD LIMIT INDICATES LLD NOT MET NUCLIDE LLD LLD LIMIT UCI/ML UCI/ML MN-54 5. 651E-09 1.5E-08
-A(f&eevvt c-t FE-59 9. 619E-09 3. OE-08 CO-58 4. 578E-09 1.5E-08 d* <
CO-60 5.855E-09 1. 5E-08 ZN-65 1. 191E-08 3. OE-08 ZR-95 7.436E-09 1. 5E-08 NB-95 5.347E-09 1. 5E-OS 1-131 4.580E-09 1. SE-OS CS-134 5.577E-09 1.SE-0O CS-137 4.816E-09 BA-140 1. 605E-08 1. SE-08
- LA-140 4. 579E-09 1.5E-08